Page 1 of 132

DOE Review Release 03/21/2023

Monitoring Feasibility Evaluation for Exotic 

Radionuclides Produced by the Oak Ridge 

National Laboratory Isotopes Division

ORAUT-RPRT-0090 Rev. 01

Effective Date: 03/10/2023

Supersedes: Revision 00

Subject Expert(s): Joseph S. Guido

Document Owner 

Approval: Signature on File

Pat McCloskey, Document Owner

Approval Date: 03/04/2023

Concurrence: Vickie S. Short Signature on File for

Kate Kimpan, Project Director

Concurrence Date: 03/06/2023

Approval: Signature on File

Timothy D. Taulbee, Associate Director for Science

Approval Date: 03/10/2023

FOR DOCUMENTS MARKED AS A TOTAL REWRITE, REVISION, OR PAGE CHANGE, REPLACE THE PRIOR 

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.

New Total Rewrite Revision Page Change
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 2 of 132

PUBLICATION RECORD

EFFECTIVE

DATE

REVISION

NUMBER DESCRIPTION

03/29/2018 00 New report evaluating the Oak Ridge National Laboratory capability 

to monitor internal exposure to exotic radionuclides that were 

produced by the laboratory’s Isotopes Division. Incorporates formal 

internal and NIOSH review comments. Initiated by Joseph S. Guido.

03/10/2023 01 Document revised to address comments received following SC&A 

review as well as during Working Group discussions. Specific 

changes include clarifying the document’s scope and intent as being 

an evaluation of ORNL monitoring capabilities regarding work by 

Isotope Group employees or within Isotope Group facilities. 

Accordingly, Appendix C (“Dose Reconstruction Approach for 

Iodine”) was removed and will be included in a separate document.

Incorporates formal internal and NIOSH review comments.

Constitutes a total rewrite of the document. Training is not required. 

Initiated by Pat McCloskey and authored by Joseph S. Guido.
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 3 of 132

TABLE OF CONTENTS

SECTION TITLE PAGE

Acronyms and Abbreviations ............................................................................................................... 5

1.0 Purpose ................................................................................................................................... 6

2.0 Scope....................................................................................................................................... 6

3.0 Isotope Production ................................................................................................................... 6

3.1 ORNL Facilities ............................................................................................................ 7

3.2 Y-12 Facilities............................................................................................................... 8

3.3 Material Transfers......................................................................................................... 9

4.0 Evaluation of Bioassay Program and Data ............................................................................... 9

4.1 Sampling Program........................................................................................................ 9

4.2 ORNL Bioassay Data ................................................................................................. 10

4.3 NOCTS Bioassay Data............................................................................................... 13

5.0 Evaluation of In Vivo Monitoring Counting Program ............................................................... 16

6.0 Inventory Development .......................................................................................................... 18

7.0 Feasibility Analysis................................................................................................................. 25

7.1 Initial Evaluation ......................................................................................................... 25

7.2 Additional Evaluation .................................................................................................. 41

8.0 Summary ............................................................................................................................... 45

References ........................................................................................................................................ 46

ATTACHMENT A SUMMARY OF IN VITRO BIOASSAY METHODS.......................................... 55

ATTACHMENT B SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER 

ANALYSIS ...................................................................................................... 63

LIST OF TABLES

TABLE TITLE PAGE

4-1 Urine bioassay codes used at ORNL, 1955 to 1988............................................................... 11

4-2 Fecal bioassay codes in use at ORNL, 1955 to 1988............................................................. 12

4-3 Bioassay code 000 with monitored nuclide, 1955 to 1988 ...................................................... 12

4-4 NOCTS versus ORNL database comparison of sample frequency by year............................ 14

4-5 NOCTS versus ORNL database comparison of sample frequency by analyte code............... 15

4-6 Gross beta samples in NOCTS and ORNL datasets (analyte codes 013 and GB0) ............... 15

5-1 Tabulation of in vivo counts from database versus annual reports ......................................... 17

6-1 Sources of radionuclide production information...................................................................... 19

6-2 Radionuclides added to inventory due to target rupture events .............................................. 19

6-3 Information added during logbook review............................................................................... 20

6-4 Final radionuclide inventory for Isotopes Division................................................................... 21
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 4 of 132

7-1 Comparison of 35S production and number of reported bioassay samples ............................. 26

7-2 Results of feasibility analysis for 1955 to 1969....................................................................... 27

7-3 Results of feasibility analysis for 1970 to 1988....................................................................... 33

7-4 Thirty-four radionuclides identified as needing additional evaluation ...................................... 40

7-5 Derived air concentration values for 28 radionuclides requiring further evaluation ................. 41

7-6 Dosimetric analysis of radionuclides ...................................................................................... 43

7-7 Number of bioassay samples collected for code 000 analytes by year................................... 44

LIST OF FIGURES

FIGURE TITLE PAGE

3-1 General layout of isotope facilities............................................................................................ 8

3-2 Isotope production flow, 1955 to 1965...................................................................................... 9
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 5 of 132

ACRONYMS AND ABBREVIATIONS

Ci curie

cm centimeter

cpm counts per minute

d day

DAC derived air concentration

DOE U.S. Department of Energy

HP health physics

hr hour

ICRP International Commission on Radiological Protection

in. inch

keV kiloelectron-volt (1,000 electron-volts)

m meter

mCi millicurie

min minute

mL milliliter

MPC maximum permissible concentration

mrem millirem

NBS National Bureau of Standards

NIOSH National Institute for Occupational Safety and Health

NOCTS NIOSH-Division of Compensation Analysis and Support Claims Tracking System

ORAU Oak Ridge Associated Universities

ORAUT ORAU Team

ORNL Oak Ridge National Laboratory

SEC Special Exposure Cohort

SRDB Ref ID Site Research Database Reference Identification (number)

WBC whole body count

yr year

Y-12 Y-12 Plant

μCi microcurie
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 6 of 132

1.0 PURPOSE

This report evaluates the Oak Ridge National Laboratory (ORNL) capabilities for internal monitoring of 

radionuclides produced by the Isotopes Division and its predecessors from 1955 to 1988. This 

evaluation was initiated after the publication of the Special Exposure Cohort (SEC) evaluation report 

for ORNL (SEC-00189) [NIOSH 2012]. As a result of the SEC-00189 ER, a class was added to the 

SEC from the beginning of ORNL operations (June 17, 1943) through July 31, 1955. The SEC 

addressed isotopes of uranium, plutonium, thorium, and mixed fission products but did not evaluate 

the dose reconstruction feasibility for radionuclides produced by the isotopes group. Because the 

class recommended in the SEC-00189 evaluation report covered the entire period petitioned, NIOSH 

closed the SEC-189 petition evaluation. 

Throughout this document the term exotic refers to radionuclides produced by the isotopes group to 

generally delineate these radionuclides from those more globally handled at the facility (e.g., uranium, 

plutonium and mixed fission and activation products). Because of the potential challenges involved in 

monitoring intakes from such a wide variety of materials, NIOSH requested this evaluation; its

purpose is to identify any areas where dose reconstruction might be infeasible. The evaluation 

methodology entailed the following steps:

• Identifying radionuclides produced by the Isotopes Division, 

• Identifying available ORNL Health Physics (HP) program bioassay methodologies, 

• Chronological benchmarking of the available bioassay methods against the radionuclide 

inventory to identify potential gaps in monitoring capability, and

• Identify areas where bioassay monitoring gaps exist. 

2.0 SCOPE

The period under evaluation in this report is August 1, 1955, through December 31, 1988. The start 

date was selected to coincide with the end of the SEC period [NIOSH 2012]. The end date coincides 

with the end of large-scale isotope production at ORNL. All operations under evaluation were 

managed by ORNL. Although most of the facilities were on the ORNL campus (many in an area 

termed “Isotope Circle”), the Isotope Division also used the cyclotron and calutron facilities at the 

Y-12 Plant. This report evaluates the capability of the ORNL HP program to monitor all materials that 

were produced and handled by the Isotopes Division, regardless of production location, in order to 

determine if bioassay technology deficiencies existed that could result in improper monitoring. The 

scope of this report is limited to isotope production activities; it excludes treatment of decontamination 

and decommissioning, site-wide construction, and maintenance activities that may encompass these 

same facilities. Although this report identifies potential dose reconstruction challenges, it is not an 

evaluation of whether a co-exposure model approach could be developed for every radionuclide.

3.0 ISOTOPE PRODUCTION

Isotope production occurred at both ORNL and Y-12 under ORNL management. At times, Y-12 

workers supported efforts at the facilities and, in some cases, Y-12 employees were administratively 

transferred to ORNL. Note that the facilities listed in this report are the primary facilities used by the 

isotopes group and are presented for a historical perspective. The inventory listing was developed 

independent of the facility list but instead was related to isotope group activities across the site.
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 7 of 132

3.1 ORNL FACILITIES

In the late 1940s, ORNL initiated a program to replace the wartime temporary structures with more 

permanent buildings. A major focus of this program was the provision for a radioisotope complex of 10 

buildings designed for processing, packaging, and shipping radioisotopes [Carver and Slater 1994].

Isotopes are produced in reactors; extracted by chemical processes; and then used for biological, 

medical, and industrial research. As early as 1946, radioisotopes were produced in the Oak Ridge 

Research Reactor. In 1947, the Isotopes Section (later Division) was formed at the Clinton 

Laboratories. By 1950, ORNL was distributing (by order) over 50 radioisotopes to research centers 

around the world.

Figure 3-1 shows the radioisotope buildings constructed under this expansion, which are grouped in 

an area termed “Isotope Circle.” The ten buildings, one stack, and their original designations were:

• 3028 Radioisotope Processing Building F,

• 3029 Radioisotope Processing Building E,

• 3030 Radioisotope Processing Building D,

• 3031 Radioisotope Processing Building C,

• 3032 Radioisotope Processing Building B,

• 3033 Radioisotope Processing Building A,

• 3034 Radioisotope Service Building,

• 3036 Decontamination Building,

• 3037 Radioisotope Area Office Building,

• 3038 Radioisotope Analytical and Pack Building, and

• 3039 Exhaust Stack.

One building (3038) was used for the analysis, storage, packaging, and shipment of materials. Six 

small buildings (3028 to 3033) were dedicated to radioisotope production and development, each 

having dedicated shielding and remote-handling capabilities. The use of dedicated small areas for 

material processing was purposeful to minimize interaction between different processing areas and to 

minimize the potential number of exposed individuals within each operational area [Thompson 1952].

The Fission Products Development Laboratory (Building 3517) was completed in 1958. It was 

originally designed and built to separate kilocurie quantities of 137Cs, 90Sr, 144Ce, and 147Pm from liquid 

reduction-oxidation and plutonium-uranium extraction waste streams. The facility was modified in 

1963 to allow production of megacurie amounts of 137Cs, 90Sr, and 144Ce, primarily for use in the 

Systems for the Nuclear Auxiliary Power program [Martin Marietta Energy Systems (MMES) 1986].

In 1962, Building 3047 was built to house the Radioisotopes Development Laboratory for research 

and development and to produce radioisotopes. The radioactive materials the Isotopes Division 

handled included 90Sr, 137Cs, 152Eu, 154Eu, 238Pu, 111mSn, 166Dy/Ho, 186Re, and 188W/188Re. A single 

sealed source of 90Sr had activity as high as 350,000 Ci [MMES 1995].
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 8 of 132

Figure 3-1. General layout of isotope facilities [Carver and Slater 1994].

3.2 Y-12 FACILITIES

Concurrently with production of isotopes in reactors on the ORNL campus, the Isotopes Division 

involved the use of the cyclotron and calutron facilities on the Y-12 site to produce isotopes.

The calutron (electromagnetic separation) facilities were originally built to separate uranium isotopes 

and recover uranium enriched in 235U. With the successful operation of the gaseous diffusion process, 

the calutrons were phased out as a production operation for enriching uranium.

By the end of 1950, plans were made to use the calutron facilities to separate the isotopes of 

plutonium to allow more accurate measurement of their nuclear properties. The first isotope to be 

separated was to be 240Pu, followed by 242Pu and 244Pu. Before 1962, radioisotope production in the 

Y-12 facility was limited to small quantities of plutonium and uranium that were produced in one or two 

calutrons in Track 5 of Building 9204-3, which was functionally separated from the other calutrons. In 

1962, a containment facility was built in Building 9204-3 that included separations areas, chemical 

processing areas, a change room, and a locker room. The actinide area operated continuously from 

1962 to 1972 and chiefly separated isotopes of plutonium and uranium but included many other 

isotopes:

• Americium-241, -242, -243;

• Beryllium-9, -10;

• Calcium-40, -41, -42, -43, -44, -46, -48;

• Curium-243, -244, -245, -246, -247, -248, -250;
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 9 of 132

• Lead-201, -204, -205, -206, -207, -208;

• Plutonium-238, -239, -240, -241, -242, -244;

• Promethium-146, -147;

• Samarium-147, -148, -149, -150, -151, -152, -154;

• Thorium-228, -230, -232; and

• Uranium-232, -233, -234, -235, -236, -238. 

3.3 MATERIAL TRANSFERS

Figure 3-2 shows the production flow between ORNL, Y-12, and offsite locations. Certain 

radionuclides were produced at the ORNL Graphite Reactor, the cyclotron, and the calutrons. Some 

materials containing exotic radionuclides were shipped off site right after production, while others 

underwent further processing at ORNL first.

Figure 3-2. Isotope production flow, 1955 to 1965 [NIOSH 2012]. 

4.0 EVALUATION OF BIOASSAY PROGRAM AND DATA

4.1 SAMPLING PROGRAM

ORNL has collected urine and fecal samples from individuals suspected of potential intakes from 

1945 (and possibly as early as 1943) to the present. The processing of urine samples at the ORNL 

Urinalysis Building started in 1947 [Davis and Warden 1954] and was performed by the ORNL Body 

Fluids Analysis group [Burnett 1948]. 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 10 of 132

Urine samples were collected based on the Area Health Physicist’s knowledge of field conditions 

(e.g., known spills or incidents, air and contamination sample results). A June 1950 document, 

Procedure for the Collection of Urine Samples, indicates that it was ORNL policy to “collect and 

analyze certain body fluids of all employees who work with large quantities of uranium, plutonium, and 

other types of radioactive materials” [Hart 1950]. This procedure gave the responsibility for the 

selection of individuals for urine bioassay to the area HP staff. Urine samples were to be submitted 

along with a request form (Form X-386) indicating, among other things, the type and quantity of 

radioactivity with which the individual worked. A March 1954 revision to this procedure included 

consideration of the need to make a second request for sample submission and made use of the 

same request format [Warden 1954]. By 1957, the sampling request was revised to include a list of 

routine analytes that could be requested (H-3, polonium, plutonium, radium, strontium, uranium, gross 

alpha, and gross beta) along with a space to write in a radionuclide name.

In earlier years, the element of concern was extracted chemically from the biological sample and the 

total radioactivity of the element in the extract was measured. At some point after the extraction and 

sample count, the total sample activity was attributed to a specific radionuclide. Many of the isotopic 

assignments were based on process knowledge because isotope-specific analyses were not possible 

or routinely performed.

To evaluate the effectiveness of its bioassay program, and as a possible basis for improvement, 

ORNL conducted a study of all urinalysis samples from July 2, 1953, to August 23, 1954 [Davis and 

Warden 1954]. The total number of samples was 1,265. ORNL concluded that the method for that 

period seemed adequate. They recommended that a major emphasis be placed on obtaining samples 

for employees regularly working with radioactive materials and that the sampling schedule be left at 

the discretion of the HP area surveyor. It was further recommended that the surveyor annually select 

at random a number of employees who do not work regularly with radioactive materials and suggest 

to them that they submit a sample.

Infrequently, a request was made for determination of a radionuclide not included in the routine 

procedure. Such determinations were usually made by the use of, or modification of, existing 

analytical methods from the literature [Henley 1968]. 

Attachment A summarizes the initial development of ORNL bioassay methods. The discussion in this 

attachment provides detail up through the initial deployment of each bioassay method.

4.2 ORNL BIOASSAY DATA

The Oak Ridge Associated Universities Team (ORAUT) obtained a copy of the ORNL bioassay 

database dated April 28, 2013 [UT-Battelle 2013]. This database contains the results of 

104,957 individual bioassay samples from September 7, 1949, through December 21, 1988. Of these, 

there are 94,988 with collection dates during the period under evaluation in this report. These 

94,988 samples (3,121 fecal; 91,867 urine) were collected from 7,564 individual workers and 

subjected to analysis for 62 different individually identified analytes and code 000, which indicates 

other. This code indicates a nonstandard analytical method. There were 1,532 code 000 urine 

samples from 502 individuals, 52 code “OO0” urine samples from 33 individuals, and 140 code “OF0” 

fecal samples for 64 individuals (note that the combination of capital “O” and numeral “0” in a code is 

not a transcription error.) Tables 4-1 and 4-2 provide a summary of the bioassay methods the ORNL 

bioassay database lists for urine and fecal samples, respectively.
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 11 of 132

Table 4-1. Urine bioassay codes used at ORNL, 1955 to 1988. 

Bioassay 

code Description/analyte

Number of 

samples Period in use

000 Other 1,532 1955,1958,1961,1963–1974,1976–1977,1979–1983,1985

OO0a Other 52 1986–1988

001 S-35 3 1958–1959,1961

002 Co-60 14 1961–1963

003 Pb-210 3 1960

004 Na-24 2 1960

005 Zr-95/Nb-95 13 1960–1963

006 Tc-99 11 1960–1964

007 As-74 6 1960

008 Br-82/Br-83 6 1960–1961

009 Fe-59 11 1960,1964

010 Mn-54 3 1960,1978

011 I-131 13 1958,1961–1964

012 Cs-132 2 1961

013 Gross beta 153 1955,1960–1964

014 Ba-140 1 1961

015 Sb-125 18 1962–1963

016 Tl-204 7 1962

017 Np-237 12 1962–1964

018 Ag-110m 1 1963

AM0 Am-241 1 1987

C-14 C-14 67 1986–1988

CM0 Cm-244 11 1986,1988

CO0 Co-60 144 1963,1965,1967–1969,1972–1976,1982,1984,1987–1988

CS0 Cesium beta 1,589 1964–1970,1972–1977,1980–1988

CS7 Cs-137 284 1955–1957,1959–1964

FP0 Fission products 17 1956–1958

FU0 Total rare earth 1,333 1959–1967,1969–1978,1980,1985

GA0 Gross alpha 132 1965–1973,1975,1979–1980

GB0 Gross beta 26 1961,1965–1966,1968–1971,1973,1984

GD0 Gd-153 40 1987–1988

GG0 Gross gamma 9 1972,1984,1986–1988

GU0 Gross alpha 12,759 1955–1964

HY3 H-3 5,680 1955–1988

I25 I-125 8 1987–1988

I31 I-131 25 1987–1988

NP0 Np-237 64 1965–1970,1972,1978–1979

PA0 Pa-231 12 1968–1973,1975,1977

PA3 Pa-233 155 1955–1958,1960–1961,1964–1966,1969–1971,1975

PH2 P-32 232 1957–1965,1968–1969,1973–1976,1978–1984

PM7 Pm-147 5 1987

PO0a Po-210 48 1955–1957,1960–1961,1963,1966–1967,1975,1979

PU0 Pu-239 15,016 1964–1988

PU1 Pu-241 147 1968–1974,1976–1979,1981–1985

PU9 Pu-239 1,738 1957–1958,1960–1964

RA0 Ra-226 329 1955–1961,1963,1966,1968,1976–1977

RA6 Ra-226 1 1987

RU6 Ru-106 81 1958,1960,1962–1967,1972,1985

SR0 Sr-90 26,408 1955–1988

SR5 Sr-85 11 1960,1987

SR9 Sr-89 368 1960–1962,1966,1969
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 12 of 132

Table 4-1. Urine bioassay codes used at ORNL, 1955 to 1988 (continued). 

Bioassay 

code Description/analyte

Number of 

samples Period in use

TA0 Ta-180 2 1986

TP0 Trans plutonium alpha 8,162 1958,1964,1966–1988

URO Uranium 15,100 1955–1988

All codes Total 91,867 1955–1988

a. The combination of capital “O” and numeral “0” in a code type is not a transcription error.

Table 4-2. Fecal bioassay codes in use at ORNL, 1955 to 1988. 

Bioassay 

code Description/analyte

Number of 

samples Period in use

OF0a Other 140 1964–1970,1976,1983,1988

GF0 Gross alpha 2,195 1955–1968,1972,1975

PF0 Pu-239 109 1968–1973,1975–1983

PF3 Pa-233 79 1957–1958,1961

RF0 Rare earth 70 1955,1960,1963–1965,1971–1972

SF0 Sr-90 243 1957–1958,1960–1974,1980

SF9 Sr-89 42 1960

TF0 Trans plutonium 178 1968–1983,1986

UF0 Uranium 65 1956,1963–1965,1968–1969,1973–1976,1979–1980

All codes Total 3,121 1955–1988

a. The combination of capital “O” and numeral “0” in a code type is not a transcription error.

To assess the target radionuclide associated with the 1532 code 000 bioassay samples, the ORAU

Team examined both the data already on file for 114 workers in the NIOSH-Division of Compensation 

Analysis and Support Claims Tracking System (NOCTS) as well as the bioassay cards for 

388 individuals that are not in that system. The Team reviewed the bioassay card data to identify the 

analyte and compile the bioassay information into a data file. A total of 1,584 individual urine bioassay 

samples were identified for 492 individuals.1 These samples were analyzed for 53 different analytes.

Table 4-3 provides a summary of the reported analytes for these code 000 samples. Note that the 

bioassay cards for the 140 code OF0 (fecal) and 52 code OO0 (urine) samples were not requested.

1 The ORNL bioassay database is known to be incomplete (some samples were not entered into the database). 

Therefore, it is expected that the number of database samples and the number of samples from the bioassay cards for 

individuals identified in the database might not be equal.

Table 4-3. Bioassay code 000 with monitored nuclide, 1955 to 1988. 

Bioassay code Description/analyte Number of samples Period in use

000 Am 60 1965–1967

000 Am-241 21 1965–1967

000 Am-243 2 1968

000 Bk-249 7 1965, 1969

000 C-14 14 1968, 1970–1973, 1979, 1982

000 Ca-45 19 1965–1966, 1968

000 Cd-109 1 1973

000 Ce 1 1969

000 Cl-36 3 1968

000 Cm 469 1965–1967

000 Cm-242 53 1965–1967

000 Cm-244 17 1965–1967

000 Co-57 2 1965

000 Co-60 4 1961, 1963, 1983

 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 13 of 132

Table 4-3. Bioassay code 000 with monitored nuclide, 1955 to 1988 (continued). 

Bioassay code Description/analyte Number of samples Period in use

000 Cr 2 1964

000 Cr-51 4 1964, 1968, 1976

000 Cs-132 1 1961

000 Eu-152 2 1985

000 Eu-154a 1 1988

000 Eu-155a 1 1988

000 Fe-55 5 1983

000 Fe-59 2 1964–1965

000 Ga-66/67 5 1970

000 Ga-67 3 1968, 1971

000 Gd-153 1 1987

000 I 64 1963, 1965–1973, 1976

000 I-125 1 1976

000 I-131 51 1958, 1965–1967, 1969–1971, 1973–1974

000 Ir-192 2 1981

000 Nb-95 2 1968–1969

000 P-32 2 1968

000 Pa 1 1965

000 Pm 3 1965–1966

000 Pm-147 2 1967

000 Pu-241 74 1967

000 Ru 29 1968–1969, 1971

000 Ru-103 2 1965

000 Ru-103/106 4 1969

000 Ru-106 9 1968–1969, 1971–1972

000 S-35 5 1955, 1968

000 Tc 12 1965, 1979–1980

000 Tc-99 9 1976–1977, 1979, 1981, 1983

000 Th 2 1965

000 Tl-201 1 1981

000 Tm-170 1 1968

000 TrPu 575 1961–1962, 1964–1969, 1974

000 W 1 1966

000 Y-88 2 1961

000 Y-90 1 1982

000 Zn-65 1 1968

000 Zr 20 1959, 1963, 1967–1969

000 Zr-95 2 1966, 1969

000 ZrNb 17 1964, 1968–1969

All codes Total 1,584 1955–1988

a. Analytical results associated with mixed nuclide release, not an individual nuclide.

4.3 NOCTS BIOASSAY DATA

Bioassay data for 1,003 workers in NOCTS were compiled into a spreadsheet. These 

1,003 individuals represent the total pool of ORNL workers in NOCTS with bioassay data when the 

ORAU Team data transcription project was initiated in mid-2014. Although the purpose of this 

transcription project was to compile a dataset for potential use as a source of ORNL coworker data, 

the data were used in this report evaluation to ascertain the degree to which the ORNL bioassay 

database represents the analysis types that were used for individual workers from August 1, 1955, 

through December 31, 1988. This was done by comparing the data in the NOCTS claim files (i.e., 

from individual bioassay cards) with the data in the ORNL database for the same individuals. This 

comparison was made for analytes containing more than 10 samples.
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 14 of 132

With the exception of gross beta analysis (results of which seem to be missing from the ORNL 

database between 1955 and 1959), the sample frequency in the ORNL and NOCTS datasets are 

comparable, although the NOCTS data files tend to be more complete. Tables 4-4 and 4-5 show the 

results of this evaluation by sample year and by analytical method code, respectively.

Table 4-4. NOCTS versus ORNL database comparison of sample 

frequency by year (for analytical methods with >10 samples). 

Year

NOCTS 

sample count

ORNL database 

sample count N/Oa

1955 485 467 1.04

1956 448 415 1.08

1957 562 517 1.09

1958 905 863 1.05

1959 674 615 1.10

1960 900 875 1.03

1961 1,010 864 1.17

1962 1,232 1,046 1.18

1963 1,330 1,157 1.15

1964 1,119 998 1.12

1965 1,170 982 1.19

1966 1,057 909 1.16

1967 878 760 1.16

1968 805 659 1.22

1969 870 733 1.19

1970 702 572 1.23

1971 687 533 1.29

1972 530 470 1.13

1973 701 578 1.21

1974 515 429 1.20

1975 360 342 1.05

1976 433 397 1.09

1977 311 297 1.05

1978 324 312 1.04

1979 271 267 1.01

1980 265 259 1.02

1981 194 194 1.00

1982 330 323 1.02

1983 254 245 1.04

1984 254 249 1.02

1985 213 209 1.02

1986 225 217 1.04

1987 172 168 1.02

1988 188 186 1.01

Overall 20,374 18,107 1.13

a. N/O = NOCTS Sample Count / ORNL Sample Count-Analytical Methods with 

>10 total samples (000, CS0, CS7, FU0, GA0, GF0, GU0, HY3, PA3, PF0, 

PH2, PU, PU0, PU1, PU9, RA0, RF0, SF0, SR9, TF0, TP0, UF0, UR0).
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 15 of 132

Table 4-5. NOCTS versus ORNL database comparison of 

sample frequency by analyte code (for analytical methods 

with >10 samples). 

Analyte code

NOCTS 

sample count

ORNL database 

sample count N/Oa

000 362 298 1.21

CS0 432 367 1.18

CS7 56 49 1.14

FU0 297 273 1.09

GA0, GU0, Pu, 

PU0, PU9

6,558 5,777 1.14

GF0 581 543 1.07

HY3 836 809 1.03

PA3 17 12 1.42

PF0 35 26 1.35

PH2 31 28 1.11

PU1 22 20 1.10

RA0 72 64 1.13

RF0 15 13 1.15

RU6 45 27 1.67

SF0 41 38 1.08

SR0 5,761 5,091 1.13

SR9 66 66 1.00

TF0 34 27 1.26

TP0 1,904 1,691 1.13

UF0 20 17 1.18

UR0 3,189 2,871 1.11

Overall 20,374 18,107 1.13

a. N/O = NOCTS Sample Count/ORNL Sample Count-Analytical 

Methods with >10 total samples (‘000’, CS0, CS7, FU0, GA0, GF0, 

GU0, HY3, PA3, PF0, PH2, PU, PU0, PU1, PU9, RA0, RF0, SF0, 

SR9, TF0, TP0, UF0, UR0).

To summarize, the ratio of the number of samples for the same group of individuals in NOCTS to that 

in the ORNL Database is 1.13:1.00. The ratio ranges from 1:1 to 1:1.29 when grouped by year 

(Table 4-4), and from 1:1 to 1:1.67 when grouped by method (Table 4-5). Note that the higher 

variance when grouped by analytical method is likely due to the smaller sample set for some of the 

groups (in comparison with the sets grouped by year). The results are consistent with the conclusion 

of the ORNL Internal Dosimetry staff that the database is incomplete and might be missing up to 25% 

of the bioassay samples [ORAUT 2013], albeit comparison between NOCTS and the ORNL database 

indicate a slightly lower value. Note that this evaluation is only qualitative.

As indicated above, the ORNL database does not contain gross beta results (analyte codes 013 and 

GB0) between 1955 and 1959. Table 4-6 shows the number of gross beta samples for the same 

group of individuals when viewed in the NOCTS dataset versus the ORNL database.

Table 4-6. Gross beta samples in NOCTS and ORNL datasets 

(analyte codes 013 and GB0). 

Dataset 1955 1956 1957 1958 1959

NOCTS 1 5 26 28 7

ORNL 0 0 0 0 0

This analysis indicates a discrepancy in the presence of gross beta samples (Analyte 013 and GB0) in 

the ORNL dataset. A review of the underlying data indicates that it was not uncommon for the gross 

beta analysis to be performed in conjunction with either fission product analysis (FP0), rare earth 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 16 of 132

analysis (FU0), or strontium analysis (SR0). The results of these accompanying FP0, FU0, or SR0 

analyses are in the ORNL database, but the gross beta results are not. It appears that gross beta 

sample results were not recorded in the ORNL database between 1955 and 1959. However, it is not 

clear from the data results if the FP0, FU0, or SR0 analyses were initiated as a result of the gross 

beta analysis result.

5.0 EVALUATION OF IN VIVO MONITORING COUNTING PROGRAM

The main whole body count (WBC) room (a shielded vault) was erected in Building 2008 on July 24, 

1959, with a 14-in.-thick pre-World War II steel shield. The first recorded background count was made 

on July 13, 1959, before the door and the roof were completed. The count room was initially used 

primarily for counting biological samples, such as milk, grass, and cow thyroids [Watts et al. 1995]. 

Use of the WBC facility for personnel monitoring began in June 1960. The system was configured with 

a 200-channel tube-type analyzer connected to a single 4- by 4-in. NaI(Tl) crystal. This configuration 

was initially used to measure 19 individuals involved in known contamination events. From June 1960 

to July 1961, the effort was expanded to include an additional 208 persons. The system was then 

upgraded to a 512-channel analyzer connected to two 8-in.-diameter by 4-in. NaI(Tl) detectors 

[Morgan 1961]. 

During the second year of operations (1961 to 1962), improvements in data analysis were instituted 

that used computer software and additional data handling (i.e., inclusion of paper tape recording).

Counter use was again focused on known or suspected internal exposures and resulted in 142 

measurements of 102 additional individuals [Morgan 1962]. Starting in 1963, the scope of the 

counting program was expanded to include routine counting of potentially exposed persons as well as 

baseline counts on individuals before entry into areas with potential for internal exposure. System 

capacity was reported at 110 persons per month; and 492 individuals were counted between 1962 

and 1963.

By 1964, continued improvements in instrumentation, scheduling, and operations made it possible to 

further increase system throughput. Between 1963 and 1964, a total of 1,568 counts were performed 

on 1,370 individuals. Emphasis was placed on routine counting of persons, who were suspected of 

having experienced an exposure or having a potential for exposure, and on obtaining baseline counts.

The 1964 HP Division annual report indicated that “the increased rate of individual counting made it 

possible to expand the base-line counting and obtain counts on essentially all persons with even a 

remote chance for exposure” [Morgan et al. 1964]. 

The goal to obtain a baseline count on essentially every person with a potential for future exposure 

was completed in May 1965 [Morgan et al. 1965]. Beginning in May, the method of selecting 

individuals was changed to allow selection by Applied HP personnel. A five-part priority system was 

implemented, as follows:

1. Persons suspected of having sustained an exposure,

2. Persons being recounted as follow-up to initial elevated in vivo counts,

3. Persons who worked directly with radioactive materials,

4. Persons who worked in the areas where radioactive materials are handled, but who did not 

work directly with the materials, and

5. Newly hired or other persons for baseline counts before beginning work with radioactive 

materials.
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 17 of 132

Based on these criteria, individuals who worked directly with radioactive materials were supposed to 

have been monitored quarterly, and those who worked where radioactive material was present were 

to have been monitored semiannually. Baseline counts were to be taken for new hires or other 

persons requiring a baseline count, and a limited number of workers were to be monitored before 

termination [Morgan et al. 1965]. 

By the beginning of the 1966 fiscal year (July 1965), the operation of the whole body counter was 

reported as being used for “the routine monitoring and evaluation of the extent of exposure to gammaemitting radioisotopes of all Laboratory employees” [Morgan et al. 1966]. The implementation of this 

routine monitoring effort was reported to be effective beginning in “the next fiscal year” (i.e., July 

1967) due to logistical problems with implementation. As stated in the 1966 HP Division annual report, 

“...the effort required for selection of workers, the frequency of the counts of the workers, preparation 

of paperwork proved to be greater than anticipated. The new routine counting program is expected to 

get under way with the beginning of the new fiscal year.”

Although the 1967 HP Division annual report indicates that baseline and specified monitoring 

frequencies continued to be implemented, contemporary ORNL dosimetry staff indicated that a 

centrally controlled in vivo monitoring program did not exist at ORNL until approximately 1994 when 

site internal dosimetrists became responsible for identifying personnel for counting [ORAUT 2004]. 

Before then, Area HP selected individuals for in vivo monitoring based on an understanding of the 

exposure potential. The Area HP staff was responsible for determining the radioisotopes to which a 

worker could be exposed as well as the counting frequencies.

Table 5-1 shows the number of in vivo counts taken each calendar year from the ORNL database 

[UT-Battelle 2013] and the HP Division annual reports from before 1983. (The HP Division reports 

after 1982 have not been found). The annual report data were assessed to fill in the gaps in the ORNL 

dataset, which only lists counts starting in 1962.

Table 5-1. Tabulation of in vivo counts from database versus annual reports. 

Year

Number of in vivo counts 

from ORNL databasea

Number of in vivo counts 

from annual reportsb

Source

(annual report)

1961 0 329 Hart 1964, p. 26

1962 71 395 Hart 1963, p. 19

1963 921 1,054 Hart 1964, p. 26

1964 1,555 1,644 UCC 1965, p. 77

1965 1,169 1,222 UCC 1966, pp. 79–80

1966 696 740 UCC 1967, pp. 85–86

1967 966 983 UCC 1968, pp. 83–84

1968 968 964 UCC 1969, pp. 77–78

1969 1,057 1,108 UCC 1970, p.67

1970 518 530 UCC 1971, p. 11

1971 324 332 UCC 1972, p. 11

1972 259 272 UCC 1973, p. 11

1973 325 350 UCC 1974, p. 14

1974 278 278 UCC 1975, p. 17

1975 330 331 UCC 1976, p. 16

1976 255 255 UCC 1977, p. 14

1977 291 291 UCC 1978, p. 14

1978 306 305 UCC 1979, p. 15

1979 402 460 UCC 1980, p. 14

1980 700 750 UCC 1981, p. 15

1981 557 590 UCC 1982, p. 18

1982 556 650 UCC 1983, p. 19

1983 411 Not available Not Applicable
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 18 of 132

Table 5-1. Tabulation of in vivo counts from database versus annual reports

(continued).

Year

Number of in vivo counts 

from ORNL databasea

Number of in vivo counts 

from annual reportsb

Source

(annual report)

1984 476 Not available Not Applicable

1985 525 Not available Not Applicable

1986 682 Not available Not Applicable

1987 681 Not available Not Applicable

1988 753 Not available Not Applicable

a. Source data from UT-Battelle [2013]. 

b. Includes number of wound counts.

6.0 INVENTORY DEVELOPMENT 

A detailed inventory of the radionuclides the ORNL Isotopes Division produced and processed was 

developed using source documents in the ORAU Team Site Research Database (SRDB). In addition, 

the Team used documents it had collected for development of the ORNL and Y-12 site profiles, and 

during subsequent visits to capture data about radionuclide production activities. The predominant 

source data for this inventory included isotope shipping and sales reports as well as various 

operational and technical report series, as shown in Table 6-1. These data sources, as well as other 

ad hoc (nonseries) reports in the SRDB, were used to develop an initial inventory of radionuclides and 

quantities. The resultant inventory represents materials produced by the Isotopes group as opposed 

to a more general inventory of materials present at the site. For example, individual fission product 

radionuclides contained within unprocessed reactor fuels are not included within the inventory 

quantities.

The initial radionuclide listing was reviewed to determine if the produced materials were handled in 

the ORNL processing facilities or (as in the case of many cyclotron materials) shipped directly off site 

for processing. Materials that were irradiated at ORNL but processed off site were identified as either 

“special irradiations” or “service irradiations.” Because these materials were not handled in an 

unsealed form at ORNL or Y-12, they were not included in the isotope inventory. Thirty-six 

radionuclides were identified in this category and removed from the initial inventory. The exception to 

this was the case where a target otherwise identified as a service irradiation ruptured. Fifty (50) 

documents related to target rupture events were identified by a keyword search of the SRDB. Another 

49 documents were identified through a review of the ORNL incident listing [UT-Battelle 2012]. In 

each event of a target rupture, the relevant radionuclide was retained in the radionuclide inventory if 

initially present. In a small number of cases, the radionuclide that was identified in the target rupture 

documentation was not contained on the previously identified inventory and was added (Table 6-2). 

Two radionuclides (123mTe and 128Te) were identified in the inventory development but were removed 

because they are effectively stable with half-lives of 9.2 × 1016 years and 2.4 × 1024 years, 

respectively).

The ORAU Team reviewed a collection of logbooks in the ORNL records repository. These logbooks 

were selected from a master listing of over 17,000 logbooks. Logbook categories matching those in 

the table below were selected to narrow the review to 1,867 logbooks. Of these, 15,961 pages from 

823 logbooks were selected for data capture. During the course of the data capture, the ORNL 

radionuclide inventory listing was referenced so that radionuclides in logbook entries that were not 

listed on the existing inventory could be identified and subsequently added to the radionuclide 

inventory listing. As a result of this review, 26 additional radionuclides were identified, and one or 

more additional inventory years were identified for 19 radionuclides (Table 6-3). Table 6-4 provides 

the final inventory list based on the above-listed data sources.
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 19 of 132

Table 6-1. Sources of radionuclide production information. 

Report series name

Publication 

frequency Start End Source

Chemical Technology Division Annual Progress 

Report

Annual 1957 1988 ORAUT 2022a

Electronuclear Research Division Annual Progress 

Report

Annual 1957 1961 ORAUT 2022b

Isotope Separations Progress Report Monthly 1976 1978 ORAUT2022c

Isotopes Development Center Progress Report 

Curium Program

Variable 1962 1964 ORAUT 2022d

Isotopes Development Center Progress Report 

Fission Products

Variable 1962 1962 ORAUT 2022e

Isotopes Development Center Progress Report 

Isotopes Separations

Variable 1962 1964 ORAUT 2022f

Isotopes Development Center Progress Report 

Radioactive Source Development

Variable 1962 1963 Beauchamp 1963

Isotopes Development Center Progress Report 

Reactor and Cyclotron Produced Isotopes

Variable 1963 1963 ORAUT 2022g

Isotopes Development Center Progress Report 

Target Development

Variable 1962 1963 ORAUT 2022h

Isotopes Development Center newsletter Variable 1967 1967 Rupp 1968

Isotopes Division Quarterly Report Quarterly 1960 1961 ORAUT 2022i

Isotopes Division Research and Development Report Monthly 1962 1962 ORAUT 2022j

List of Radioisotope Customers with Summary of 

Radioisotope Shipments

Annual 1964 1988 ORAUT 2022k

ORNL Status and Progress Report Monthly 1950 1967 ORAUT 2022l

Quantity Data on Radioisotopes Quarterly 1959 1964 ORAUT 2022m

Radioisotope Cost-Price Study Annual 1957 1974 ORAUT 2022n

Radioisotope Distribution Program Progress Report Monthly 1973 1980 ORAUT 2022o

Radioisotope Inventory Monthly 1956 1966 ORAUT 2022p

Radioisotope Production and Process Development 

Annual Report

Annual 1954 1956 ORAUT 2022q

Radioisotope Program (8000) Progress Report Monthly 1969 1973 ORAUT 2022r

Review of Radioisotopes Program Annual 1964 1967 ORAUT 2022s

Stable Isotope and Heavy Element Inventories Monthly 1961 1969 ORAUT 2022t

Transuranium Processing Plant Semiannual Report 

of Production, Status, and Plan

Semiannual 1969 1975 ORAUT 2022u

Table 6-2. Radionuclides added to 

inventory due to target rupture events. 

Radionuclide Year(s)

As-71 1960

As-72 1960

As-74 1958, 1960–1961

Mn-52 1960

Mn-54 1960

Sr-85 1961

Y-88 1961

Cs-132 1962
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 20 of 132

Table 6-3. Information added during logbook review. 

Radionuclide Information addeda Year(s) Sources

Beryllium-7 Production year 1962 Butler 1962, p. 9

Sodium-22 Production year 1964 Coleman 1964, p. 4

Chlorine-38 Radionuclide 1956 Cain 1956, p. 8

Scandium-46 Production year 1973 Poggenburg 1972, p. 9

Vanadium-48 Radionuclide 1962 Burrell 1962a, p. 17

Manganese-54 Production year 1963 Butler 1962, p. 25

Cobalt-57 Production year 1964 Millspaugh 1964, p. 12

Nickel-66 Radionuclide 1968 Sillyman 1967, p. 52

Copper-64 Production year 1976 Poggenburg 1972, p. 18

Copper-67 Production year 1963 Butler 1962, p. 26

Gallium-68 Radionuclide 1971 Golden 1970, p. 7

Bromine-85 Radionuclide 1963 Burrell 1962b, p. 15

Rubidium-88 Radionuclide 1964 Coleman 1963b, p. 8

Yttrium-86 Radionuclide 1964

1968

Millspaugh 1964, p. 19;

Butler 1967, p. 55

Zirconium-97 Radionuclide 1971 Guinn 1970, p. 3

Niobium-92 Radionuclide 1963 Hill 1962b, p. 125

Ruthenium-97 Production year 1970 Poggenburg 1969, p. 6

Ruthenium-105 Radionuclide 1956 Warden 1956, p. 9

Indium-114m Radionuclide 1975 Poggenburg 1972, p. 113

Tin-117m Radionuclide 1977 Poggenburg 1976, p. 8

Tellurium-132 Radionuclide 1963

1968

Arthur 1962, p. 17;

Miller 1967, p. 17

Barium-135m Production year 1970 Poggenburg 1969, p. 24

Praseodymium144Radionuclide 1962 Davis 1961, p. 131

Promethium-145 Radionuclide 1968 Sillyman 1967, p. 56

Promethium-148 Radionuclide 1970 Miller 1969, p. 6

Europium-152 Production years 1962

1968

Hill 1962a, p. 5; Butler 1962b, p. 7;

Butler 1967, p. 40

Gadolinium-148 Radionuclide 1970 Hill 1969, p. 4

Terbium-156 Production year 1968 Butler 1968, p. 3

Golden 1966, p. 143

Terbium-158 Radionuclide 1970 Poggenburg 1969, p. 49

Holmium-166 Radionuclide 1968 Butler 1967, p. 45

Erbium-171 Radionuclide 1973 Poggenburg 1972, p. 26

Polonium-210 Radionuclide 1962

1966

Davis 1962, p. 5;

Wallace 1966, p. 10

Thorium-228 Radionuclide 1962 Butler 1962b, p. 9

Protactinium-231 Production years 1961

1962

Burden 1961, p. 6; Burden 1961, p. 16;

Butler 1962a, p. 3

Protactinium-233 Radionuclide 1963

1964

1966

1969

Hill 1962b, p. 22; Coleman 1963a, p. 9;

Miller 1965, p. 4; Burrell 1967, p. 11

Uranium-232 Production years 1961

1962

1965

Burden 1961, p. 13; Butler 1962b, p. 4;

Keny 1965, p. 5

Neptunium-236 Radionuclide 1965 Walters 1965, p. 44

Neptunium-237 Production years 1961

1962

Burden 1961, p. 10; Butler 1962b, p. 3;

Butler 1962a, p. 5 

Neptunium-238 Radionuclide 1965

1966

Clark 1963, p. 11; Coleman 1963c, p. 18
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 21 of 132

Table 6-3. Information added during logbook review (continued).

Radionuclide Information addeda Year(s) Sources

Curium-242 Production years 1962

1964

Butler 1962b, p. 6; Butler 1962, p. 11; 

Millspaugh 1963, p. 26

Curium-244 Production year 1962 Davis 1961, p. 151

Berkelium-249 Production year 1964 Moore 1964, p. 3–71

Californium-252 Production year 1962 Butler 1962a, p. 9

Einsteinium-252 Radionuclide 1970 Butler 1969, p. 12

Fermium-257 Production years 1969

1970

Guinn 1968, p. 9;

Hill 1969, p. 3

a. “Production year” indicates additional inventory year for nuclide already on inventory or Radionuclide. “Radionuclide” 

indicates addition to nuclide not previously identified on inventory. 

Table 6-4. Final radionuclide inventory for Isotopes Division. 

Nuclide Production years

Hydrogen-3 1955–1957, 1959–1988

Beryllium-7 1955, 1957–1959, 1962, 1964, 1969

Carbon-11 1975, 1977, 1979–1980

Carbon-14 1955–1975, 1980–1983, 1985

Sodium-22 1955–1956, 1961–1964

Sodium-24 1955–1967

Magnesium-28 1966, 1969–1970, 1977, 1983–1984, 1987–1988

Phosphorus-32 1955–1967

Phosphorus-33 1964–1965, 1967–1987

Sulfur-35 1955–1969

Chlorine-36 1955–1972

Chlorine-38 1956

Argon-37 1955–1957, 1959–1971, 1973–1982

Potassium-40 1979

Potassium-42 1955–1966

Potassium-43 1964–1965, 1967, 1971, 1973–1978, 1980–1981, 1983

Calcium-41 1977, 1986

Calcium-45 1955–1966

Calcium-47 1960–1984

Scandium-46 1955–1957, 1959–1973

Scandium-49 1955, 1965

Titanium-44 1956, 1958

Vanadium-48 1962

Chromium-51 1955–1967, 1975

Manganese-52 1960

Manganese-54 1955–1957, 1960, 1963–1965

Iron-55 1955–1956, 1959–1966, 1980–1986

Iron-59 1955–1956, 1958–1967

Cobalt-56 1967, 1972, 1977

Cobalt-57 1955–1957, 1964, 1972–1976

Cobalt-58 1955–1957, 1959–1965

Cobalt-60 1955–1988

Nickel-63 1955–1957, 1959–1972, 1978, 1980, 1985–1987

Nickel-66 1968

Copper-64 1955–1969, 1976

Copper-67 1963–1964, 1967–1968, 1970–1971, 1973–1976

Zinc-65 1955–1957, 1959–1966

Zinc-69m 1967, 1973–1974

Gallium-67 1958–1959, 1969–1978, 1983

Gallium-68 1971

Gallium-72 1955, 1957, 1960–1970
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 22 of 132

Table 6-4. Final radionuclide inventory for Isotopes Division (continued). 

Nuclide Production years

Arsenic-71 1960

Arsenic-76 1956–1957, 1959–1967

Arsenic-77 1956–1957, 1959–1966

Selenium-75 1955–1957, 1959–1966, 1979–1986

Bromine-82 1956–1967

Bromine-85 1963

Krypton-85 1955–1988

Rubidium-83 1969

Rubidium-84 1964–1965, 1969, 1975

Rubidium-86 1955–1957, 1959–1972

Rubidium-88 1964

Strontium-82 1970

Strontium-85 1955, 1957–1967, 1970, 1986

Strontium-87m 1960, 1964, 1970

Strontium-89 1955–1957, 1959–1963, 1965–1987

Strontium-90 1955–1988

Yttrium-86 1964, 1968

Yttrium-88 1957–1958, 1961–1963, 1965, 1974

Yttrium-90 1956–1968, 1973, 1987–1988

Yttrium-91 1955–1957, 1959–1978

Zirconium-95 1955–1986

Zirconium-97 1971

Niobium-90 1957

Niobium-92 1963

Niobium-92m 1967

Niobium-95 1955–1957, 1959–1981, 1983–1985

Molybdenum-93 1957, 1962

Molybdenum-99 1957, 1959–1971

Technetium-95m 1957–1958, 1967, 1970

Technetium-99 1955–1957, 1959–1970, 1972–1988

Technetium-99m 1966, 1968, 1970

Ruthenium-97 1959–1960, 1962, 1970

Ruthenium-103 1955–1957, 1959–1986

Ruthenium-105 1956

Ruthenium-106 1955–1957, 1959–1988

Rhodium-102 1958

Palladium-103 1962, 1964

Palladium-109 1957, 1959–1971

Silver-110m 1955–1957, 1959–1966

Silver-111 1956–1957, 1959–1970

Cadmium-109 1957–1958, 1960–1961, 1963–1966, 1972

Cadmium-115 1955–1956, 1960, 1962–1966

Cadmium-115m 1955–1956, 1960–1966

Indium-111 1969–1971, 1973

Indium-114 1955–1957, 1959–1977, 1981

Indium-114m 1975

Tin-113 1955–1957, 1959–1967, 1979

Tin-117m 1977

Tin-119m 1986

Antimony-122 1956, 1959–1968, 1971, 1987

Antimony-124 1955–1957, 1959–1967

Antimony-125 1955–1957, 1959–1966
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 23 of 132

Table 6-4. Final radionuclide inventory for Isotopes Division (continued). 

Nuclide Production years

Arsenic-74 1957–1959, 1961, 1965

Arsenic-72 1960

Tellurium-121 1957

Tellurium-132 1963, 1968

Iodine-123 1965, 1967–1970

Iodine-125 1957, 1961–1964

Iodine-129 1955–1957, 1959–1988

Iodine-130 1960–1972, 1985

Iodine-131 1955–1976, 1978–1980, 1983, 1985–1986, 1988

Iodine-132 1967–1972

Iodine-133 1961, 1967–1968, 1977

Xenon-127 1983, 1987–1988

Xenon-133 1960–1976, 1978–1980

Cesium-131 1965

Cesium-132 1962

Cesium-134 1955–1957, 1959–1966

Cesium-137 1955–1988

Barium-131 1955–1957, 1959–1971

Barium-133 1955–1957, 1959–1972

Barium-135m 1970, 1986

Barium-140 1955–1957, 1959–1968, 1970–1978, 1980–1981, 1983

Lanthanum-140 1955–1957, 1959–1966, 1987

Cerium-139 1955, 1957–1958

Cerium-141 1955–1957, 1959–1966, 1970

Cerium-144 1955–1979, 1981–1988

Praseodymium-142 1956–1957, 1959–1968, 1970

Praseodymium-143 1955–1957;1959–1968, 1970, 1972–1973

Praseodymium-144 1962

Neodymium-140 1969

Neodymium-147 1955–1957, 1959–1973, 1979

Neodymium-149 1979

Promethium-145 1968

Promethium-146 1974

Promethium-147 1955–1968, 1970–1987

Promethium-148 1970

Samarium-151 1968–1982, 1984–1987

Samarium-153 1956–1957, 1959–1961, 1963–1969

Europium-152a 1962, 1968, 1974–1975, 1978–1981, 1984–1985, 1988

Europium-155 1955–1957, 1959–1968, 1975

Gadolinium-148 1970

Gadolinium-153 1971, 1973–1988

Terbium-156 1958, 1967–1968

Terbium-158 1970

Dysprosium-157 1975

Dysprosium-159 1957, 1961

Dysprosium-166 1965, 1984

Holmium-156 1965

Holmium-166 1968

Erbium-171 1973

Thulium-170 1962–1971, 1974–1975

Thulium-171 1967

Ytterbium-169 1980, 1986

Hafnium-181 1955, 1957, 1959–1977, 1979–1980
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 24 of 132

Table 6-4. Final radionuclide inventory for Isotopes Division (continued). 

Nuclide Production years

Tantalum-182 1955–1957, 1959–1972, 1974

Tungsten-181 1957–1958

Tungsten-185 1955–1957, 1959–1971

Tungsten-187 1955–1957, 1959–1970

Rhenium-186 1957, 1959–1972, 1979

Osmium-185 1957, 1966

Osmium-191 1957, 1959–1970, 1984

Iridium-192 1955–1968, 1970–1971, 1973–1988

Iridium-194 1959, 1961, 1963, 1968

Platinum-195m 1972–1974, 1978

Platinum-197 1965

Gold-195 1961

Gold-198 1955, 1957–1966

Gold-199 1955, 1957, 1959–1967

Mercury-197 1957–1966

Mercury-203 1955–1957, 1959–1967

Thallium-201 1975

Thallium-204 1955–1971

Lead-203 1972–1973

Bismuth-206 1957–1958

Bismuth-207 1957

Bismuth-210 1955–1957, 1959–1970

Polonium-210 1962, 1966

Thorium-228 1962

Thorium-229 1968, 1970–1971, 1973–1974, 1977, 1979–1986, 1988

Thorium-230 1956, 1962–1963, 1965, 1967–1976, 1978–1988

Thorium-232 1963, 1968–1969, 1972–1976, 1978–1987

Thorium-234 1981

Protactinium-231 1961–1963, 1965–1966, 1968–1969, 1976–1981, 

1984–1986

Protactinium-233 1963–1964, 1966, 1969

Uranium-232 1961–1965, 1968, 1970–1971, 1974–1979

Uranium-233 1961–1963, 1965–1988

Uranium-234 1956, 1961–1963, 1965–1988

Uranium-235 1955–1957, 1961–1963, 1965–1988

Uranium-236 1955–1956, 1961–1963, 1965–1988

Uranium-238 1955–1956, 1961–1988

Neptunium-236 1965

Neptunium-237 1955–1957, 1959, 1961–1962, 1964–1965, 1967–1968, 

1970, 1972–1987

Neptunium-238 1965–1966

Plutonium-236 1968, 1970, 1973, 1975, 1981, 1984, 1986

Plutonium-237 1984, 1986

Plutonium-238 1961–1963, 1965, 1968–1985, 1987–1988

Plutonium-239 1955–1956, 1961–1972, 1974–1985, 1987–1988

Plutonium-240 1961–1966, 1968–1986, 1988

Plutonium-241 1955–1956, 1959, 1962–1975, 1977–1986

Plutonium-242 1961–1988

Plutonium-244 1968, 1970–1982

Americium-241 1959–1988

Americium-243 1961–1978, 1980–1986, 1988

Curium-242 1962–1966, 1968, 1986

Curium-243 1965, 1972–1973, 1975–1976, 1981–1983

Curium-244 1962–1964, 1966–1988
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 25 of 132

Table 6-4. Final radionuclide inventory for Isotopes Division (continued). 

Nuclide Production years

Curium-245 1969, 1972–1973, 1986

Curium-246 1970–1971, 1973, 1977, 1988

Curium-247 1969, 1972

Curium-248 1968–1980, 1982–1984, 1986, 1988

Berkelium-249 1964, 1967, 1969–1984, 1986, 1988

Californium-248 1972

Californium-249 1968–1976, 1979–1982, 1984, 1986

Californium-250 1970, 1973–1976, 1980

Californium-252 1962, 1967–1988

Californium-253 1984

Einsteinium-252 1970

Einsteinium-253 1967–1981, 1984, 1986, 1988

Einsteinium-254 1972–1974, 1980, 1982, 1984, 1988

Fermium-255 1984, 1988

Fermium-257 1968–1977, 1980, 1984, 1986, 1988

a. Inventory entries listed as “Eu-152, Eu-154” were compiled as 152Eu.

7.0 FEASIBILITY ANALYSIS

7.1 INITIAL EVALUATION

The annual production history for each of the 213 radionuclides in Table 6-4 was compared to the 

available in vitro bioassay methods for each year (Tables 4-1, 4-2, 4-3, and 4-6) and in vivo bioassay 

methods (Section 4.0) in each year. The information from the analysis of NOCTS bioassay data 

(Section 4.2) was incorporated to augment the listing of available methods (namely for gross beta) 

during periods for which the ORNL dataset does not include those methods. The ORAU Team

determined if ORNL had monitoring capability for each radionuclide in each production year by taking 

into consideration the characteristic radionuclide emissions (type and energy) and analytical method 

sensitivity (including chemical specificity, radiation type, and energy). The ORAU Team performed this 

evaluation to identify potential gaps in monitoring capabilities specific to an individual radionuclide. No 

attempt was made to reconcile the quantity of a specific radionuclide against the frequency at which a 

particular monitoring method was used.

In this evaluation, when an adequate monitoring method was indicated (i.e., by analytical results for a 

previous year), it was deemed adequate evidence for concluding there was no gap in monitoring 

capability. This was the case even when a particular radionuclide was produced in a later year in 

which no instances of that bioassay method were evident. That is, once a bioassay method was 

reported, it was assumed to be available each year thereafter. For example, 35S was produced each 

year between 1955 and 1969 but analytical results for methods capable of detecting 35S were only 

reported in 1955, 1958, 1959, and 1961 (Table 7-1). The lack of recorded monitoring results for the 

other years of interest was not considered indicative of a gap in monitoring capability. 

Tables 7-2 and 7-3 provide a summary of the results of the monitoring capability evaluation. Color and 

letter codes in Tables 7-2 and 7-3 identify specific radionuclides in inventory, indicate if a bioassay 

method was available to detect the radionuclide, and specify if sample results for that particular 

bioassay method are available for that particular year. For instances where dose would be bounded 

by external radiation (i.e., noble gases), “EXT” is indicated as the bioassay method. As stated in 

International Commission on Radiological Protection (ICRP) Publication 30, Section 8.2.3, “for 

submersion in radioisotopes of the noble gases, external irradiation will be of such overriding 

importance that it alone need be considered” [ICRP 1979].
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 26 of 132

Table 7-1. Comparison of 35S production and number 

of reported bioassay samples. 

Year Inventory (Ci) S-35 samples reported

1955 57 1

1956 14 0

1957 67 0

1958 88 1

1959 60 1

1960 23 0

1961 150 1

1962 70 0

1963 29 0

1964 100 0

1965 14 0

1966 83 0

1967 0.1 0

1968 0.1 0

1969 0.01 0

In Tables 7-2 and 7-3, colors and letters mean:

• Green or G

– A specific radionuclide was present in inventory in the specified year; and

– A bioassay method was available to detect the radionuclide in the specified year; and

– Sample results for that particular bioassay method are available for the specified year.

• Yellow or Y

– A specific radionuclide was present in inventory in the specified year; and

– A bioassay method was available to detect the radionuclide, but no sample results for 

that particular bioassay method are available for the specified year.

• Red or R

– A specific radionuclide was present in inventory in the specified year, but an additional 

analysis was necessary to determine if the nuclide represented an infeasibility from a 

monitoring perspective.

• No color or N

– No radionuclide was present in inventory in the specified year.

Of the 213 identified radionuclides, the ORAU Team determined that the ORNL HP program was able 

to monitor for 179 of them using an existing monitoring method (green or yellow shading, or coded as 

[G] or [Y]). For these 179 radionuclides, no further analysis was required. Attachment B summarizes 

the radiological properties and monitoring capability decisions for these nuclides.
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2022 Page 27 of 132

Table 7-2. Results of feasibility analysis for 1955 to 1969.

a

Nuclide Bioassay method code

b 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69

Hydrogen-3 HY3GGGNGGGGGGGGGGG

Beryllium-7 SC

b

RNRRRNNGNGNNNNG

Carbon-11 SCNNNNNNNNNNNNNNN

Carbon-14 000(C-14); 013/GB0;C14GGGGGGGGGGGGYGG

Sodium-22 013/GB0;SCGGNNNNGGGGNNNNN

Sodium-24 013/GB0;004;SCGGGGGGGGGGGGGNN

Magnesium-28 SCNNNNNNNNNNNGNNG

Phosphorus-32 000(P-32); PH2GGGGGGGGGGGYYNN

Phosphorus-33 013/GB0NNNNNNNNNGGNYGG

Sulfur-35 000(S-35);001GYYGGYGYYYYYYGY

Chlorine-36 000(Cl-36); 013/GB0GGGGGGGGGGGGYGG

Chlorine-38 013/GB0NGNNNNNNNNNNNNN

Argon-37 EXTGGGNGGGGGGGGGGG

Potassium-40 SCNNNNNNNNNNNNNNN

Potassium-42 013/GB0;SCGGGGGGGGGGGGNNN

Potassium-43 SCNNNNNNNNNGGNGNN

Calcium-41(c)NNNNNNNNNNNNNNN

Calcium-45 000(Ca-45); 013/GB0GGGGGGGGGGGGNNN

Calcium-47 013/GB0;SCNNNNNGGGGGGGGGG

Scandium-46 013/GB0; FU0; SCGGGNGGGGGGGGGGG

Scandium-49 013/GB0; FU0GNNNNNNNNNGNNNN

Titanium-44 013/GB0NGNGNNNNNNNNNNN

Vanadium-48 SCNNNNNNNGNNNNNNN

Chromium-51 000(Cr-51); SC

c

RRRRRRRGGGGGGNN

Manganese-52 013/GB0NNNNNGNNNNNNNNN

Manganese-54 010;SC

c

RRRNNGNNGGGNNNN

Iron-55 000(Fe-55)

c

RRNNRRRRRRRRNNN

Iron-59 000(Fe-59); 

013/GB0;009;SC G G N G G G G G G G G G G N N 

Cobalt-56 SCNNNNNNNNNNNNGNN

Cobalt-57 000(Co-57); SC

c

RRRNNNNNNGNNNNN

Cobalt-58 013/GB0;SCGGGNGGGGGGGNNNN

Cobalt-60 000(Co-60); 

013/GB0;002;CO0;SC G G G G G G G G G G G G G G G 

Nickel-63 013/GB0GGGNGGGGGGGGYGG

Nickel-66 013/GB0NNNNNNNNNNNNNGN

Copper-64 013/GB0GGGGGGGGGGGGYGG

Copper-67 SCNNNNNNNNGGNNGGN

Zinc-65 000(Zn-65); 013/GB0;SCGGGNGGGGGGGGNNN
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2022 Page 28 of 132

Table 7-2. Results of feasibility analysis for 1955 to 1969 (continued).

a

Nuclide Bioassay method code

b 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69

Zinc-69m GB0NNNNNNNNNNNNYNN

Gallium-67 000(Ga-67); SC

c

NNNRRNNNNNNNNNG

Gallium-68 SCNNNNNNNNNNNNNNN

Gallium-72 013/GB0; SCGNGNNGGGGGGGGGG

Arsenic-71 013/GB0NNNNNGNNNNNNNNN

Arsenic-72 013/GB0NNNNNGNNNNNNNNN

Arsenic-74 007; 013/GB0;SCNNGGGNGNNNGNNNN

Arsenic-76 013/GB0;SCNGGNGGGGGGGGGNN

Arsenic-77 013/GB0NGGNGGGGGGGGNNN

Selenium-75 SC

c

RRRNRRRGGGGGNNN

Bromine-82 008, 0013/GB013;SCNGGGGGGGGGGGGNN

Bromine-85 013/GB0NNNNNNNNGNNNNNN

Krypton-85 EXTGGGGGGGGGGGGGGG

Rubidium-83 SCNNNNNNNNNNNNNNG

Rubidium-84 SCNNNNNNNNNGGNNNG

Rubidium-86 013/GB0;SCGGGNGGGGGGGGGGG

Rubidium-88 SCNNNNNNNNNGNNNNN

Strontium-82 SCNNNNNNNNNNNNNNN

Strontium-85 SR5; SC

c

RNRRRGYGGGGGYNN

Strontium-87m SC

c

NNNNNRNNNGNNNNN

Strontium-89 SR0;SR9; 013/GB0;GGGNGGGGGNGGGGG

Strontium-90 SR0GGGGGGGGGGGGGGG

Yttrium-86 SCNNNNNNNNNGNNNGN

Yttrium-88 000(Y-88); 013/GB0; 

FU0;SC N N G G N N G G G N G N N N N 

Yttrium-90 000(Y-90); FU0NGGGGGGGGGGGGYN

Yttrium-91 013/GB0; FU0GGGNGGGGGGGGGYG

Zirconium-95 000(Zr-95)005; 

013/GB0;SC G G G G G G G G G G G G G G G 

Zirconium-97 SCNNNNNNNNNNNNNNN

Niobium-90 013/GB0NNGNNNNNNNNNNNN

Niobium-92 SCNNNNNNNNGNNNNNN

Niobium-92m SCNNNNNNNNNNNNGNN

Niobium-95 000(Nb-95); 005; 

013/GB0;SC G G G N G G G G G G G G G G G 

Molybdenum-93 (c)NNRNNNNRNNNNNNN

Molybdenum-99 013/GB0;SCNNGNGGGGGGGGGGG

Technetium-95m 013/GB0;SCNNGGNNNNNNNNGNN
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2022 Page 29 of 132

Table 7-2. Results of feasibility analysis for 1955 to 1969 (continued).

a

Nuclide Bioassay method code

b 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69

Technetium-99 000(Tc-99); 006; 

013/GB0 G G G N G G G G G G G G Y G G 

Technetium-99m SCNNNNNNNNNNNGNGN

Ruthenium-97 013/GB0NNNNGGNGNNNNNNN

Ruthenium-103 000(Ru-103); SC

c

RRRNRRRGGGGGGGG

Ruthenium-105 013/GB0NGNNNNNNNNNNNNN

Ruthenium-106 000(Ru-106); 013/GB0; 

RU6 G G G N G G G G G G G G G G G 

Rhodium-102 013/GB0NNNGNNNNNNNNNNN

Palladium-103 (c)NNNNNNNRNRNNNNN

Palladium-109 013/GB0NNGNGGGGGGGGYGG

Silver-110m 013/GB0;018;SCGGGNGGGGGGGGNNN

Silver-111 013/GB0NGGNGGGGGGGGYGG

Cadmium-109 000(Cd-109)

c

NNRRNRRNRRRRNNN

Cadmium-115 013/GB0GGNNNGNGGGGGNNN

Cadmium-115m 013/GB0GGNNNGGGGGGGNNN

Indium-111 SCNNNNNNNNNNNNNNG

Indium-114 013/GB0GGGNGGGGGGGGYGG

Indium-114m SCNNNNNNNNNNNNNNN

Tin-113 SC

c

RRRNGGGGGGGGGNN

Tin-117m SCNNNNNNNNNNNNNNN

Tin-119m (c)NNNNNNNNNNNNNNN

Antimony-122 013/GB0;SCNGNNGGGGGGGGGGN

Antimony-124 013/GB0;SCGGGNGGGGGGGGGNN

Antimony-125 013/GB0;015;SCGGGNGGGGGGGGNNN

Tellurium-121 (c)NNRNNNNNNNNNNNN

Tellurium-132 SCNNNNNNNNGNNNNGN

Iodine-123 THNNNNNNNNNNGNGGG

Iodine-125 000(I-125); I25; TH

c

NNRNNNRGGGNNNNN

Iodine-129 THRRRNRRRGGGGGGGG

Iodine-130 TH

c

NNNNNRRGGGGGGGG

Iodine-131 000(I-131); 011; I31; TH

c

RRRGYYGGGGGGGGG

Iodine-132 THNNNNNNNNNNNNGGG

Iodine-133 TH

c

NNNNNNRNNNNNGGN

Xenon-127 EXTNNNNNNNNNNNNNNN

Xenon-133 EXTNNNNNGGGGGGGGGG

Cesium-131 (c)NNNNNNNNNNRNNNN

Cesium-132 000(Cs-132); 012; SCNNNNNNNGNNNNNNN

Cesium-134 013/GB0;SCGGGNGGGGGGGGNNN
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2022 Page 30 of 132

Table 7-2. Results of feasibility analysis for 1955 to 1969 (continued).

a

Nuclide Bioassay method code

b 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69

Cesium-137 CS7;CS0; SCGGGGGGGGGGGGGGG

Barium-131 SR0GGGNGGGGGGGGGGG

Barium-133 SC

c

RRRNRRRGGGGGGGG

Barium-135m SCNNNNNNNNNNNNNNN

Barium-140 014;SR0GGGNGGGGGGGGGGN

Lanthanum-140 013;FU0;SCGGGNGGGGGGGGNNN

Cerium-139 (c)RNRRNNNNNNNNNNN

Cerium-141 013/GB0;FU0GGGNGGGGGGGGNNN

Cerium-144 013/GB0;FU0;SCGGGGGGGGGGGGGGG

Praseodymium-

142

013/GB0;FU0 N G G N G G G G G G G G G G N 

Praseodymium-

143

013/GB0;FU0 G G G N G G G G G G G G G G N 

Praseodymium-

144

013/GB0;FU0 N N N N N N N G N N N N N N N 

Neodymium-140 013/GB0NNNNNNNNNNNNNNG

Neodymium-147 013/GB0;FU0GGGNGGGGGGGGGGG

Neodymium-149 013/GB0;FU0NNNNNNNNNNNNNNN

Promethium-145 (c)NNNNNNNNNNNNNRN

Promethium-146 013/GB0;FU0; SCNNNNNNNNNNNNNNN

Promethium-147 000(Pm-147); 

013/GB0;PM7; FU0 G G G G G G G G G G G G G G N 

Promethium-148 013/GB0;FU0; SCNNNNNNNNNNNNNNN

Samarium-151 013/GB0;FU0;NNNNNNNNNNNNNGG

Samarium-153 013/GB0;FU0NGGNGGGNGGGGGGG

Europium-152 000(Eu-152); SCNNNNNNNGNNNNNGN

Europium-155 000(Eu-155); 013;SCGGGNGGGGGGGGGGN

Gadolinium-148 GA0NNNNNNNNNNNNNNN

Gadolinium-153 000(Gd-153); GD0; SCNNNNNNNNNNNNNNN

Terbium-156 SC

c

NNNRNNNNNNNNGGN

Terbium-158 FU0NNNNNNNNNNNNNNN

Dysprosium-157 FU0NNNNNNNNNNNNNNN

Dysprosium-159 (c)NNRNNNRNNNNNNNN

Dysprosium-166 FU0NNNNNNNNNNGNNNN

Holmium-156 FU0; SCNNNNNNNNNNGNNNN

Holmium-166 013/GB0NNNNNNNNNNNNNGN

Erbium-171 013/GB0NNNNNNNNNNNNNNN

Thulium-170 000(Tm-170);FU0NNNNNNNGGGGGGGG

Thulium-171 FU0NNNNNNNNNNNNGNN
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2022 Page 31 of 132

Table 7-2. Results of feasibility analysis for 1955 to 1969 (continued).

a

Nuclide Bioassay method code

b 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69

Ytterbium-169 SCNNNNNNNNNNNNNNN

Hafnium-181 013/GB0GNGNGGGGGGGGYGG

Tantalum-182 013/GB0;SCGGGNGGGGGGGGGGG

Tungsten-181 (c)NNRRNNNNNNNNNNN

Tungsten-185 013/GB0GGGNGGGGGGGGYGG

Tungsten-187 013/GB0;SCGGGNGGGGGGGGGGG

Rhenium-186 013/GB0NNGNGGGGGGGGYGG

Osmium-185 SC

c

NNRNNNNNNNNGNNN

Osmium-191 013/GB0;SCNNGNGGGGGGGGGGG

Iridium-192 000(Ir-192); 

0013/GB0;SC G G G G G G G G G G G G G G N 

Iridium-194 013/GB0;SCNNNNGNGNGNNNNGN

Platinum-195m SCNNNNNNNNNNNNNNN

Platinum-197 SCNNNNNNNNNNGNNNN

Gold-195 (c)NNNNNNRNNNNNNNN

Gold-198 013/GB0; SCGNGGGGGGGGGGNNN

Gold-199 013/GB0;SCGNGNGGGGGGGGGNN

Mercury-197 SC

c

NNRRRRRGGGGGNNN

Mercury-203 013/GB0;SCGGGNGGGGGGGGGNN

Thallium-201 000(Tl-201); SCNNNNNNNNNNNNNNN

Thallium-204 013/GB0;016GGGGGGGGGGGGYGG

Lead-203 SCNNNNNNNNNNNNNNN

Bismuth-206 (c)NNRRNNNNNNNNNNN

Bismuth-207 013/GB0NNGNNNNNNNNNNNN

Bismuth-210 013/GB0GGGNGGGGGGGGYGG

Polonium-210 004;PO0; GU0NNNNNNNGNNNGNNN

Thorium-228 GU0NNNNNNNGNNNNNNN

Thorium-229 GF0;TF0NNNNNNNNNNNNNGN

Thorium-230 GF0;TF0NGNNNNNGGNGNGGG

Thorium-232 GF0;TF0NNNNNNNNGNNNNGG

Thorium-234 013/GB0NNNNNNNNNNNNNNN

Protactinium-231 PF3;PA0NNNNNNGYYNYYNGG

Protactinium-233 PA3, SCNNNNNNNNGGNGNNG

Uranium-232 UR0NNNNNNGGGGGNNGN

Uranium-233 UR0NNNNNNGGGNGGGGG

Uranium-234 UR0NGNNNNGGGNGGGGG

Uranium-235 UR0GGGNNNGGGNGGGGG

Uranium-236 UR0GGNNNNGGGNGGGGG

Uranium-238 UR0GGNNNNGGGGGGGGG
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2022 Page 32 of 132

Table 7-2. Results of feasibility analysis for 1955 to 1969 (continued).a

Nuclide Bioassay method codeb 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69

Neptunium-236 SC N N N N N N N N N N G N N N N

Neptunium-237 017;GU0;NP0; G G G N G N G G N G G N G G N

Neptunium-238 013/GB0; SC N N N N N N N N N N G G N N N

Plutonium-236 PU0 N N N N N N N N N N N N N G N

Plutonium-237 PU0 N N N N N N N N N N N N N N N

Plutonium-238 GU0;PU0 N N N N N N G G G N G N N G G

Plutonium-239 GU0;PU9;PU0 G G N N N N G G G G G G G G G

Plutonium-240 GU0;PU0 N N N N N N G G G G G G N G G

Plutonium-241 000(Pu-241); PU1c R R N N R N N R R R R R G G G

Plutonium-242 GU0;PU0 N N N N N N G G G G G G G G G

Plutonium-244 PU0 N N N N N N N N N N N N N G N

Americium-241 000(Am-241);AM0; 

GUO;TP0 N N N N G G G G G G G G G G G 

Americium-243 000(Am-243); TP0; GF0 N N N N N N G G G G G G G G G

Curium-242 000(Cm-242); GU0; TP0 N N N N N N N G G G G G N G N

Curium-243 TP0 N N N N N N N N N N G N N N N

Curium-244 000(Cm-244); TP0;CM0 N N N N N N N G G G N G G G G

Curium-245 TP0 N N N N N N N N N N N N N N G

Curium-246 TP0 N N N N N N N N N N N N N N N

Curium-247 TP0 N N N N N N N N N N N N N N G

Curium-248 TP0 N N N N N N N N N N N N N G G

Berkelium-249 000(Bk-249); TP0 N N N N N N N N N G N N G N G

Californium-248 TP0 N N N N N N N N N N N N N N N

Californium-249 TP0 N N N N N N N N N N N N N G G

Californium-250 TP0 N N N N N N N N N N N N N N N

Californium-252 TP0; GU0 N N N N N N N G N N N N G G G

Californium-253 TP0 N N N N N N N N N N N N N N N

Einsteinium-252 TP0 N N N N N N N N N N N N N N N

Einsteinium-253 TP0 N N N N N N N N N N N N G G G

Einsteinium-254 TP0 N N N N N N N N N N N N N N N

Fermium-255 TP0 N N N N N N N N N N N N N N N

Fermium-257 TP0 N N N N N N N N N N N N N G G

a. See Section 7.1 for color coding.

b. Bioassay codes defined in Tables 4-1 and 4-2. EXT indicates exposure monitored by external dosimetry, SC indicates monitored by in vivo analysis, TH indicates 

monitored by in vivo thyroid counting.

c. See discussion in Section 7.2. 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2022 Page 33 of 132

Table 7-3. Results of feasibility analysis for 1970 to 1988.

a 

Nuclide

Bioassay

method code

b 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88

Hydrogen-3 HY3GGGGGGGGGGGGGGGGGGG

Beryllium-7 SC

c

NNNNNNNNNNNNNNNNNNN

Carbon-11 SCNNNNNGNGNGGNNNNNNNN

Carbon-14 000(C-14); 

013/GB0;C14 G G G G Y Y N N N N Y Y G Y N Y N N N 

Sodium-22 013/GB0;SCNNNNNNNNNNNNNNNNNNN

Sodium-24 013/GB0;004;SCNNNNNNNNNNNNNNNNNNN

Magnesium-28 SCGNNNNNNGNNNNNGGNNGG

Phosphorus-32 000(P-32); PH2NNNNNNNNNNNNNNNNNNN

Phosphorus-33 013/GB0GGYGYYYYYYYYYYGYYYN

Sulfur-35 000(S-35);001NNNNNNNNNNNNNNNNNNN

Chlorine-36 000(Cl-36); 

013/GB0 G G Y N 

N N N N N N N N N N N N N N N 

Chlorine-38 013/GB0NNNNNNNNNNNNNNNNNNN

Argon-37 EXTGGNGGGGGGGGGGNNNNNN

Potassium-40 SCNNNNNNNNNGNNNNNNNNN

Potassium-42 013/GB0;SCNNNNNNNNNNNNNNNNNNN

Potassium-43 SCNGNGGGGGGNGGNGNNNNN

Calcium-41 (c)NNNNNNNRNNNNNNNNRNN

Calcium-45 000(Ca-45); 

013/GB0 N N N N N N N N N N N N N N N N N N N 

Calcium-47 013/GB0;SCGGGGGGGGGGGGGGGNNNN

Scandium-46 013/GB0; FU0; 

SC G G G G N N N N N N N N N N N N N N N 

Scandium-49 013/GB0; FU0NNNNNNNNNNNNNNNNNNN

Titanium-44 013/GB0NNNNNNNNNNNNNNNNNNN

Vanadium-48 SCNNNNNNNNNNNNNNNNNNN

Chromium-51 000(Cr-51); SC

c

NNNNNGNNNNNNNNNNNNN

Manganese-52 013/GB0NNNNNNNNNNNNNNNNNNN

Manganese-54 010;SC

c

NNNNNNNNNNNNNNNNNNN

Iron-55 000(Fe-55)

c

NNNNNNNNNNRRRGYYYNN

Iron-59 000(Fe-59); 

013/GB0;009;SC N N N N N N N N N N N N N N N N N N N 

Cobalt-56 SCNNGNNNNGNNNNNNNNNNN

Cobalt-57 000(Co-57); SC

c

NNGGGGGNNNNNNNNNNNN

Cobalt-58 013/GB0;SCNNNNNNNNNNNNNNNNNNN
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2022 Page 34 of 132

Table 7-3. Results of feasibility analysis for 1970 to 1988 (continued).a 

Nuclide

Bioassay 

method code

b 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88

Cobalt-60 000(Co-60); 

013/GB0;002;CO

0;SC

G G G G G G G G G G G G G G G G G G G 

Nickel-63 013/GB0GGYNNNNNYNYNNNNYYYN

Nickel-66 013/GB0NNNNNNNNNNNNNNNNNNN

Copper-64 013/GB0NNNNNNYNNNNNNNNNNNN

Copper-67 SCGGNGGGGNNNNNNNNNNNN

Zinc-65 000(Zn-65); 

013/GB0;SC N N N N N N N N N N N N N N N N N N N 

Zinc-69m 013/GB0NNNGYNNNNNNNNNNNNNN

Gallium-67 000(Ga-67); SC

c

GGGGGGGGGNNNNGNNNNN

Gallium-68 SCNGNNNNNNNNNNNNNNNNN

Gallium-72 013/GB0; SCGNNNNNNNNNNNNNNNNNN

Arsenic-71 013/GB0NNNNNNNNNNNNNNNNNNN

Arsenic-72 013/GB0NNNNNNNNNNNNNNNNNNN

Arsenic-74 007; 013/GB0;SCNNNNNNNNNNNNNNNNNNN

Arsenic-76 013/GB0;SCNNNNNNNNNNNNNNNNNNN

Arsenic-77 013/GB0NNNNNNNNNNNNNNNNNNN

Selenium-75 SC

c

NNNNNNNNNGGGGGGGGNN

Bromine-82 008, 

0013/GB013;SC N N N N N N N N N N N N N N N N N N N 

Bromine-85 013/GB0NNNNNNNNNNNNNNNNNNN

Krypton-85 EXTGGGGGGGGGGGGGGGGGGG

Rubidium-83 SCNNNNNNNNNNNNNNNNNNN

Rubidium-84 SCNNNNNGNNNNNNNNNNNNN

Rubidium-86 013/GB0;SCGGGNNNNNNNNNNNNNNNN

Rubidium-88 SCNNNNNNNNNNNNNNNNNNN

Strontium-82 SCGNNNNNNNNNNNNNNNNNN

Strontium-85 SR5; SC

c

YNNNNNNNNNNNNNNNYNN

Strontium-87m SC

c

GNNNNNNNNNNNNNNNNNN

Strontium-89 SR0;SR9; 013/

GB0; G G G G G G G G G G G G G G G G G G N 

Strontium-90 SR0GGGGGGGGGGGGGGGGGGG

Yttrium-86 SCNNNNNNNNNNNNNNNNNNN

Yttrium-88 000(Y-88); 

013/GB0; FU0;SC N N N N G N N N N N N N N N N N N N N 

Yttrium-90 000(Y-90); FU0NNNGNNNNNNNNNNNNNYY

Yttrium-91 013/GB0; FU0GGGGGGGGGNNNNNNNNNN
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2022 Page 35 of 132

Table 7-3. Results of feasibility analysis for 1970 to 1988 (continued).a 

Nuclide

Bioassay 

method code

b 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88

Zirconium-95 000(Zr-95)005; 

013/GB0;SC G G G G G G G G G G G G G G G G G N N 

Zirconium-97 SCNGNNNNNNNNNNNNNNNNN

Niobium-90 013/GB0NNNNNNNNNNNNNNNNNNN

Niobium-92 SCNNNNNNNNNNNNNNNNNNN

Niobium-92m SCNNNNNNNNNNNNNNNNNNN

Niobium-95 000(Nb-95); 005; 

013/GB0;SC G G G G G G G G G G G G N G G G N N N 

Molybdenum-93 (c)NNNNNNNNNNNNNNNNNNN

Molybdenum-99 013/GB0;SCGGNNNNNNNNNNNNNNNNN

Technetium-95m 013/GB0;SCGNNNNNNNNNNNNNNNNNN

Technetium-99 000(Tc-99); 006; 

013/GB0 G N Y G Y Y G G Y G Y G G Y G Y Y Y Y 

Technetium-99m SCGNNNNNNNNNNNNNNNNNN

Ruthenium-97 013/GB0GNNNNNNNNNNNNNNNNNN

Ruthenium-103 000(Ru-103); SC

c

GGGGGGGGGGGGGGGGGNN

Ruthenium-105 013/GB0NNNNNNNNNNNNNNNNNNN

Ruthenium-106 000(Ru-106); 

013/GB0; RU6 G G G G G Y G G Y G G G G G G G Y Y Y 

Rhodium-102 013/GB0NNNNNNNNNNNNNNNNNNN

Palladium-103 (c)NNNNNNNNNNNNNNNNNNN

Palladium-109 013/GB0GGNNNNNNNNNNNNNNNNN

Silver-110m 013/GB0;018;SCNNNNNNNNNNNNNNNNNNN

Silver-111 013/GB0GNNNNNNNNNNNNNNNNNN

Cadmium-109 000(Cd-109)

c

NNRNNNNNNNNNNNNNNNN

Cadmium-115 013/GB0NNNNNNNNNNNNNNNNNNN

Cadmium-115m 013/GB0NNNNNNNNNNNNNNNNNNN

Indium-111 SCGGNGNNNNNNNNNNNNNNN

Indium-114 013/GB0GGYGYYYYNNNYNNNNNNN

Indium-114m SCNNNNNGNNNNNNNNNNNNN

Tin-113 SC

c

NNNNNNNNNGNNNNNNNNN

Tin-117m SCNNNNNNNGNNNNNNNNNNN

Tin-119m (c)NNNNNNNNNNNNNNNNRNN

Antimony-122 013/GB0;SCNGNNNNNNNNNNNNNNNGN

Antimony-124 013/GB0;SCNNNNNNNNNNNNNNNNNNN

Antimony-125 013/GB0;015;SCNNNNNNNNNNNNNNNNNNN

Tellurium-121 (c)NNNNNNNNNNNNNNNNNNN

Tellurium-132 SCNNNNNNNNNNNNNNNNNNN
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2022 Page 36 of 132

Table 7-3. Results of feasibility analysis for 1970 to 1988 (continued).a 

Nuclide

Bioassay 

method code

b 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88

Iodine-123 THGNNNNNNNNNNNNNNNNNN

Iodine-125 000(I-125); I25; 

THc N N N N N N N N N N 

N N N N N N N N N 

Iodine-129 THGGGGGGGGGYYYYYYYGGG

Iodine-130 TH

c

GGGNNNNNNNNNNNNYNNN

Iodine-131 000(I-131); 011; 

I31; THc G G G G G G G N G Y Y N 

N Y N Y G N G 

Iodine-132 THGGGNNNNNNNNNNNNNNNN

Iodine-133 TH

c

NNNNNNNGNNNNNNNNNNN

Xenon-127 EXTNNNNNNNNNNNNNGNNNGG

Xenon-133 EXTGGGGGGGNGGGNNNNNNNN

Cesium-131 (c)NNNNNNNNNNNNNNNNNNN

Cesium-132 000(Cs-132); 

012; SC N N N N N N N N N N N N N N N N N N N 

Cesium-134 013/GB0;SCNNNNNNNNNNNNNNNNNNN

Cesium-137 CS7;CS0; SCGGGGGGGGGGGGGGGGGGG

Barium-131 SR0GGNNNNNNNNNNNNNNNNN

Barium-133 SC

c

GGGNNNNNNNNNNNNNNNN

Barium-135m SCGNNNNNNNNNNNNNNNGNN

Barium-140 014;SR0GGGGGGGGGNGGNGNNNNN

Lanthanum-140 013;FU0;SCNNNNNNNNNNNNNNNNNGN

Cerium-139 (c)NNNNNNNNNNNNNNNNNNN

Cerium-141 013/GB0;FU0GNNNNNNNNNNNNNNNNNN

Cerium-144 013/GB0;FU0;SCGGGGGGGGGGNGGGGGGGG

Praseodymium-

142

013/GB0;FU0 G N N N N N N N N N N N N N N N N 

N N 

Praseodymium-

143

013/GB0;FU0 G N G G N N N N N N N N N N N N N 

N N 

Praseodymium-

144

013/GB0;FU0 N N N N N N N N N N N N N N N N N N N 

Neodymium-140 013/GB0NNNNNNNNNNNNNNNNNNN

Neodymium-147 013/GB0;FU0GGGGNNNNNYNNNNNNNNN

Neodymium-149 013/GB0;FU0NNNNNNNNNYNNNNNNNNN

Promethium-145 (c)NNNNNNNNNNNNNNNNNNN

Promethium-146 013/GB0;FU0; SCNNNNGNNNNNNNNNNNNNN

Promethium-147 000(Pm-147); 

013/GB0;PM7; 

FU0

G G G G G G G G G Y G Y Y Y G G Y G N 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2022 Page 37 of 132

Table 7-3. Results of feasibility analysis for 1970 to 1988 (continued).a 

Nuclide

Bioassay 

method code

b 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88

Promethium-148 013/GB0;FU0; SCGNNNNNNNNNNNNNNNNNN

Samarium-151 013/GB0;FU0;GGGGGGGGGYGYYNGGYYN

Samarium-153 013/GB0;FU0NNNNNNNNNNNNNNNNNNN

Europium-152 000(Eu-152); SCNNNNGGNNGGGGNNGGNNG

Europium-155 000(Eu-155); 

013;SC N N N N N G N N N N N N N N N N N N N 

Gadolinium-148 GA0GNNNNNNNNNNNNNNNNNN

Gadolinium-153 000(Gd-153); 

GD0; SC N G N G G G G G G G G G G G G G G G G 

Terbium-156 SC

c

NNNNNNNNNNNNNNNNNNN

Terbium-158 FU0GNNNNNNNNNNNNNNNNNN

Dysprosium-157 FU0NNNNNGNNNNNNNNNNNNN

Dysprosium-159 (c)NNNNNNNNNNNNNNNNNNN

Dysprosium-166 FU0NNNNNNNNNNNNNNYNNNN

Holmium-156 FU0; SCNNNNNNNNNNNNNNNNNNN

Holmium-166 013/GB0NNNNNNNNNNNNNNNNNNN

Erbium-171 013/GB0NNNGNNNNNNNNNNNNNNN

Thulium-170 000(Tm-170);FU0GGNNGGNNNNNNNNNNNNN

Thulium-171 FU0NNNNNNNNNNNNNNNNNNN

Ytterbium-169 SCNNNNNNNNNNGNNNNNGNN

Hafnium-181 013/GB0GGYGYYYYNYYNNNNNNNN

Tantalum-182 013/GB0;SCGGGNGNNNNNNNNNNNNNN

Tungsten-181 (c)NNNNNNNNNNNNNNNNNNN

Tungsten-185 013/GB0GGNNNNNNNNNNNNNNNNN

Tungsten-187 013/GB0;SCGNNNNNNNNNNNNNNNNNN

Rhenium-186 013/GB0GGGNNNNNNYNNNNNNNNN

Osmium-185 SC

c

NNNNNNNNNNNNNNNNNNN

Osmium-191 013/GB0;SCGNNNNNNNNNNNNNGNNNN

Iridium-192 000(Ir-192); 

0013/GB0;SC G G N G G G G G G G G G G G G G G G G 

Iridium-194 013/GB0;SCNNNNNNNNNNNNNNNNNNN

Platinum-195m SCNNGGGNNNGNNNNNNNNNN

Platinum-197 SCNNNNNNNNNNNNNNNNNNN

Gold-195 (c)NNNNNNNNNNNNNNNNNNN

Gold-198 013/GB0; SCNNNNNNNNNNNNNNNNNNN

Gold-199 013/GB0;SCNNNNNNNNNNNNNNNNNNN

Mercury-197 SC

c

NNNNNNNNNNNNNNNNNNN

Mercury-203 013/GB0;SCNNNNNNNNNNNNNNNNNNN
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2022 Page 38 of 132

Table 7-3. Results of feasibility analysis for 1970 to 1988 (continued).a 

Nuclide

Bioassay 

method code

b 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88

Thallium-201 000(Tl-201); SCNNNNNGNNNNNNNNNNNNN

Thallium-204 013/GB0;016GGNNNNNNNNNNNNNNNNN

Lead-203 SCNNGGNNNNNNNNNNNNNNN

Bismuth-206 (c)NNNNNNNNNNNNNNNNNNN

Bismuth-207 013/GB0NNNNNNNNNNNNNNNNNNN

Bismuth-210 013/GB0GNNNNNNNNNNNNNNNNNN

Polonium-210 PO0; GU0NNNNNNNNNNNNNNNNNNN

Thorium-228 GU0NNNNNNNNNNNNNNNNNNN

Thorium-229 GF0;TF0GGNGGNNGNGGGGGYYGNY

Thorium-230 GF0;TF0GGGGGGGNGGGGGGYYGYY

Thorium-232 GF0;TF0;NNGGGGGNGGGGGGYYGYN

Thorium-234 013/GB0NNNNNNNNNNNYNNNNNNN

Protactinium-231 PF3;PA0NNNNNNYGYYYYNNYYYNN

Protactinium-233 PA3, SCNNNNNNNNNNNNNNNNNNN

Uranium-232 UR0GGNNGGGGGGNNNNNNNNN

Uranium-233 UR0GGGGGGGGGGGGGGGGGGG

Uranium-234 UR0GGGGGGGGGGGGGGGGGGG

Uranium-235 UR0GGGGGGGGGGGGGGGGGGG

Uranium-236 UR0GGGGGGGGGGGGGGGGGGG

Uranium-238 UR0GGGGGGGGGGGGGGGGGGG

Neptunium-236 SCNNNNNNNNNNNNNNNNNNN

Neptunium-237 017;GU0;NP0;GNGYYYYYGGYYYYYYYYN

Neptunium-238 013/GB0; SCNNNNNNNNNNNNNNNNNNN

Plutonium-236 PU0GNNGNGNNNNNGNNGNGNN

Plutonium-237 PU0NNNNNNNNNNNNNNGNGNN

Plutonium-238 GU0;PU0GGGGGGGGGGGGGGGGNGG

Plutonium-239 GU0;PU9;PU0GGGNGGGGGGGGGGGGNGG

Plutonium-240 GU0;PU0GGGGGGGGGGGGGGGGGNG

Plutonium-241 000(Pu-241); 

PU1

c G G G G G Y N G G G Y G G G G G Y N 

N

Plutonium-242 GU0;PU0GGGGGGGGGGGGGGGGGGG

Plutonium-244 PU0GGGGGGGGGGGGGNNNNNN

Americium-241 000(Am-241); 

AM0; GUO; TP0 G G G G G G G G G G G G G G G G G G G 

Americium-243 000(Am-243); 

TP0 G G G G G G G G G N G G G G G G G N G 

Curium-242 000(Cm-242); 

TP0 N N N N N N N N N N N N N N N N G N N 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2022 Page 39 of 132

Table 7-3. Results of feasibility analysis for 1970 to 1988 (continued).a 

Nuclide

Bioassay 

method codeb 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88

Curium-243 TP0 N N G G N G G N N N N G G G N N N N N

Curium-244 000(Cm-244); 

TP0;CM0 G G G G G G G G G G G G G G G G G G G 

Curium-245 TP0 N N G G N N N N N N N N N N N N G N N

Curium-246 TP0 G G N G N N N G N N N N N N N N N N G

Curium-247 TP0 N N G N N N N N N N N N N N N N N N N

Curium-248 TP0 G G G G G G G G G G G N G G G N G N G

Berkelium-249 000(Bk-249); TP0 G G G G G G G G G G G G G G G N G N G

Californium-248 TP0 N N G N N N N N N N N N N N N N N N N

Californium-249 TP0 G G G G G G G N N G G G G N G N G N N

Californium-250 TP0 G N N G G G G N N N G N N N N N N N N

Californium-252 TP0 G G G G G G G G G G G G G G G G G G G

Californium-253 TP0 N N N N N N N N N N N N N N G N N N N

Einsteinium-252 TP0 G N N N N N N N N N N N N N N N N N N

Einsteinium-253 TP0 G G G G G G G G G G G G N N G N G N G

Einsteinium-254 TP0 N N G G G N N N N N G N G N G N N N G

Fermium-255 TP0 N N N N N N N N N N N N N N G N N N G

Fermium-257 TP0 G G G G G G G G N N G N N N G N G N G

a. See Section 7.1 for color coding.

b. Bioassay codes defined in Tables 4-1 and 4-2. EXT indicates exposure monitored by external dosimetry, SC indicates monitored by in vitro analysis, TH indicates 

monitored by in vitro thyroid counting.

c. See discussion in Section 7.2. 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 40 of 132

In the case of 34 of the 213 radionuclides (Table 7-4), the ORAU Team concluded that additional 

evaluations were necessary to determine if the nuclides represented an infeasibility from a monitoring 

perspective. Table 7-4 provides a summary of the radiological properties of these 34 radionuclides.

An analysis and evaluation of the monitoring capability of 28 of these 34 radionuclides is provided in 

Section 7.2. Separate analyses for five of the remaining six (radioiodines) are provided in a separate 

document specifically targeting assignment of internal dose from radioiodine exposure. The one 

remaining (Pu-241) was processed and handled on the Y-12 campus. Because associated exposure 

would have occurred at the Y-12 campus further analysis will be included in a Y-12 specific 

evaluation.

Table 7-4. Thirty-four radionuclides identified as needing additional evaluation.

a

Nuclide Production years Half life

Decay 

modeb

Photon 

energyc (keV)

Electron 

energyd (keV)

Beryllium-7 1955, 1957–1959, 1962, 1964, 1969 53.3 d EC 49.3 0

Calcium-41 1977, 1986 1.4E5 yr EC 0.4 2.3

Chromium-51 1955–1967, 1975 27.7 d EC 32.5 3.8

Manganese-54 1955–1957, 1960, 1963–1965 312.5 d EC 836 4.2

Iron-55 1955–1956, 1959–1966, 1980–1986 2.7 yr EC 1.6 4.2

Cobalt-57 1955–1957, 1964, 1972–1976 270.9 d EC 125.2 18.6

Gallium-67 1958–1959, 1969–1978, 1983 78.26 hr EC 158 35.5

Selenium-75 1955–1957, 1959–1966, 1979–1986 119.8 d EC 394.2 14.5

Strontium-85 1955, 1957–1967, 1970, 1986 64.84 d EC 511.8 8.9

Strontium-87m 1960, 1964, 1970 2.8 hr EC 320.3 66.9

Molybdenum-93 1957, 1962 3.5E3 yr EC 10.6 5.5

Ruthenium-103 1955–1957, 1959–1986 39.28 d EC 468.7 74.8

Palladium-103 1962, 1964 16.96 d EC 14.4 5.8

Cadmium-109 1957–1958, 1960–1961, 1963–

1966, 1972

464 d EC 26.3 82.6

Tin-113 1955–1957, 1959–1967, 1979 115.1 d EC 22.8 6.3

Tin-119m 1986 293 d IT 11.4 77.7

Tellurium-121 1957 17 d EC 577.3 9.9

Iodine-125 1957, 1961–1964 60.1 d EC 42 19.3

Iodine-129 1955–1957, 1959–1988 1.57E7 yr β– 24.6 63.8

Iodine-130 1960–1972, 1985 12.36 hr β– 2,138.5 297.2

Iodine-131 1955–1976, 1978–1980, 1983, 

1985–1986, 1988

8.04 d β– 381.5 191.7

Iodine-133 1961, 1967–1968, 1977 20.8 hr β– 607.1 410.6

Cesium-131 1965 9.69 d EC 22.8 6.5

Barium-133 1955–1957, 1959–1972 10.74 yr EC 401.9 54.2

Cerium-139 1955, 1957–1958 137.66 d EC 159.5 35.5

Promethium-145 1968 17.7 yr EC 31 14

Terbium-156 1958, 1967–1968 5.34 d EC 1,826 103.1

Dysprosium-159 1957, 1961 144.4 d EC 45 12.8

Tungsten-181 1957–1958 121.2 d EC 40.4 10.8

Osmium-185 1957, 1966 94 d EC 718.9 19.2

Gold-195 1961 183 d EC 84.6 50.7

Mercury-197 1957–1966 64.1 hr EC 70 66.4

Bismuth-206 1957–1958 6.24 d EC 3,278.1 135.8

Plutonium-241 1955–1956, 1959, 1962–1975, 

1977–1986

14.4 yr β– 0 5.2

a. Radiological properties in this table are from Radiological Toolbox [Eckerman and Shoreen 2013]. 

b. EC = decay by electron capture, IT = decay by isomeric transition, β– = decay by beta emission.

c. Emitted photon and X-ray energy per transformation.

d. Emitted beta, conversion electron, and auger electron energy per transformation.
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 41 of 132

7.2 ADDITIONAL EVALUATION 

As indicated in Table 7-5, below, 28 of the 34 radionuclides requiring additional evaluation all decay 

by either electron capture or isomeric transformation and generally have short half-lives (22 of the 28 

have half-lives of less than 1 year). 

Table 7-5. Derived air concentration values for

28 radionuclides requiring further evaluation. 

Nuclide DCF (Sv/Bq)a DACb (μCi/cm3)

Beryllium-7 4.2E−10 1.2E−05

Calcium-41 2.5E−09 3.0E−06

Chromium-51 2.5E−10 1.6E−05

Manganese-54 7.3E−09 4.7E−07

Iron-55 7.5E−09 6.1E−07

Cobalt-57 3.7E−09 9.4E−07

Gallium-67 1.7E−09 2.0E−06

Selenium-75 7.5E−09 3.3E−07

Strontium-85 5.6E−09 8.8E−07

Strontium-87m 6.0E−10 1.6E−05

Molybdenum-93 2.8E−08 4.0E−07

Ruthenium-103 1.5E−08 2.6E−07

Palladium-103 1.7E−09 1.9E−06

Cadmium-109 2.3E−07 5.9E−08

Tin-113 1.3E−08 3.0E−07

Tin-119m 1.1E−08 3.8E−07

Tellurium-121 5.4E−09 1.1E−06

Cesium-131 7.5E−10 1.3E−05

Barium-133 9.6E−09 3.1E−07

Cerium-139 1.0E−08 4.0E−07

Promethium-145 4.1E−08 2.3E−07

Terbium-156 1.4E−08 4.0E−07

Dysprosium-159 2.6E−09 2.3E−06

Tungsten-181 4.4E−10 1.3E−05

Osmium-185 7.1E−09 4.0E−07

Gold-195 8.3E−09 4.7E−07

Mercury-197 3.6E−08 1.3E−07

Bismuth-206 2.4E−08 2.7E−07

a. Most limiting inhalation dose conversion factor (Sv/Bq) from ICRP 

Publication 68 [ICRP 1994].

b. Calculated derived air concentration (DAC) based on 

contemporary ICRP [1994] DCFs. Corresponds to the air 

concentration that, if breathed at the standard rate (1.2 m3/hr) for 

2,000 hr/yr, will result in a dose equivalent of 5 rem. 

Table 7-5 lists the limiting derived air concentration (DAC) values based on solubility for each of the 

28 radionuclides under evaluation in this discussion. These values range from 1.6 × 10-5 μCi/cm3

(

87mSr) to 5.9 × 10-8 μCi/cm3

 (109Cd). For comparison purposes, before publication of National Bureau 

of Standards (NBS) Handbook 69 in 1961 the tolerance value for airborne beta/gamma activity in 

ORNL facilities was set at 1 × 10-7 μCi/cm3

. Respiratory protection was required for entry above 10% 

of this limit (1 × 10-8 μCi/cm3

). By 1961, the maximum permissible concentration (MPC) concept within 

NBS Handbook 69 [NBS 1959] was adopted. The MPC for occupational exposure to unidentified 

beta/gamma emitters was set at 1 × 10-9 μCi/cm3

 [Hart 1960] with trigger levels remaining at 0.1 MPC 

(1 × 10-10 μCi/cm3

) for general entry without respiratory protection [UCC 1961]. Information on the 

DAC values associated with the radionuclides shown in Table 7-5 along with the general standards in 

place at the time is provided to illustrate the culture around radiation safety at the time of production of 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 42 of 132

these exotics. For example, pre NBS, the respiratory protection requirements were set at values less 

than the DACs for the nuclides shown in Table 7-5. Post NBS, the standard was even more protective 

than the DACs shown in Table 7-5.

An evaluation of the dosimetric consequences of each of the 28 radionuclides requiring further 

analysis was conducted. The committed dose to the maximally exposed organ from inhalation of 

1 × 10-5 of the total annual inventory was computed for the year with the maximum recorded inventory 

(Table 7-6). The factor 1 × 10-5 was selected based on the guidance in NUREG-1400, which 

postulates that 1 × 10-6 times the material handled could serve as a reasonable estimate of the 

quantity that could be inhaled [Hickey et al. 1993]. A factor of 10 was added to ensure a conservative

evaluation. The organ dose conversion factor (mrem/mCi) for the organ with the highest unit dose per

intake was selected from ICRP [1994], as shown in the table. Although inventory quantities were not 

available for six radionuclides (93Mo, 103Pd, 139Ce, 156Tb, 185Os, and 206Bi), dose consequences 

(50-year committed dose equivalent) from inhalation of a significant fraction of the annual inventory for 

the remainder range from 0.3 mrem to 1,464 mrem to the maximally exposed organ. It should be 

noted that the inventory quantity for 55Fe in this calculation did not consider the inventory during 1980 

through 1982, during which values were as high as 1 × 106 mCi (a factor of 1,600 higher than in 

previous years). The intake quantity calculated using the analysis method would predict an intake 

quantity of 0.1 Ci, which corresponds to an air activity of 4 × 10-5 μCi/ml. Exposure to this 

concentration of 55Fe without detection by workplace monitoring controls does not seem credible, 

considering the fact that the manufacturing process for 55Fe would also carry over a small percentage 

of 59Fe (an easily detected beta/gamma emitter). The ORNL radioisotope production manual indicates 

that 59Fe is produced by the same production mechanism as 55Fe (irradiation of 54Fe) and lists its 

presence at <5%.

As indicated in Section 4.2, ORNL had an active bioassay program from the earliest period under 

evaluation (1955) and routinely performed analyses for tritium, polonium, plutonium, radium, 

strontium, uranium, gross alpha, and gross beta. When necessary, additional methods were 

developed to meet emergent sampling needs. Such supplemental sampling was coded specifically to 

the analyte (codes 001–018, as defined in Table 4-1) or was given a more general “000” code (or 0F0 

for fecal analysis).

Table 4-3 lists all of the analytes associated with the 1584 code “000” sample results that are known 

to exist (based on the ORNL bioassay database; [UT-Battelle 2013]). This listing is potentially 

incomplete because it is known that not all bioassay results were recorded into the bioassay database 

(see the discussion in Section 4.2). However, at one point bioassay analyses specific to eight of the 

28 radionuclides under evaluation (51Cr, 54Mn, 55Fe, 57Co, 67Ga, 85Sr, 103Ru, and 109Cd) were 

performed. Table 7-7 indicates the frequency of these samples.
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 43 of 132

Table 7-6. Dosimetric analysis of radionuclides. 

Nuclide

Maximum 

annual 

inventory (mCi)

Maximum 

organ DCFa

(mrem/mCi) Organa

Dose to organ from annual 

inhalation of 1 × 10-5 time 

inventoryb (mrem)

Beryllium-7 533 1,554 Extrathoracic airways 8

Calcium-41 501 9,250 Bone surface 46

Chromium-51 46,225 925 Extrathoracic airways 428

Manganese-54 115 27,010 Extrathoracic airways 31

Iron-55 620c 27,750 Spleen 172

Cobalt-57 175 13,690 Lungs 24

Gallium-67 120 6,290 Extrathoracic airways 8

Selenium-75 2,160 27,750 Kidneys 599

Strontium-85 142 20,720 Extrathoracic airways 29

Strontium-87m 84 2,220 Extrathoracic airways 2

Molybdenum-93 (d) 103,600 Bone surface (d)

Ruthenium-103 1,020 55,500 Lungs 566

Palladium-103 (d) 6,290 Extrathoracic airways (d)

Cadmium-109 64 851,000 Kidneys 545

Tin-113 610 48,100 Lungs 293

Tin-119m 3,598 40,700 Lungs 1464

Tellurium-121 (d) 19,980 Extrathoracic airways (d)

Cesium-131 25(e) 2,775 Extrathoracic airways 1

Barium-133 80 35,520 Bone surface 28

Cerium-139 (d) 37,000 Lungs (d)

Promethium-145 32 151,700 Bone surface 49

Terbium-156 (d) 51,800 Extrathoracic airways (d)

Dysprosium-159 60 9,620 Bone surface 6

Tungsten-181 18 1,628 Extrathoracic airways 0.3

Osmium-185 (d) 26,270 Extrathoracic airways (d)

Gold-195 5.6 30,710 Lungs 2

Mercury-197 542 133,200 Lungs 722

Bismuth-206 (d) 88,800 Extrathoracic airways (d)

a. DCFs are based on ICRP [1994], obtained from the Radiological Toolbox. While DCFs are provided for a multitude of 

individual organs, the highest value (along with the associated organ) is listed and was used in subsequent calculations.

b. The calculated values represents the 50-year committed dose to the organ listed based on an intake of 1E-05 times the 

listed inventory quantity.

c. Inventory quantities for 1980 to 1982 were not included in analysis.

d. No Inventory data are available for one or more years for these radionuclides.

e. Inventory data based on parent nuclide (Ba-131).
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 44 of 132

Table 7-7. Number of bioassay samples collected for code 000 analytes by year.

a

Analytical 

method code 

(radionuclide) Production years 1960 1964 1965 1968 1969 1970 1971 1973 1976 1978 1983 1987

000 (Cr) 1955–1967, 1975 NS 2 NS NS NS NS NS NS NS NS NS NS

000 (Cr-51) 1955–1967, 1975 NS 1 NS 2 NS NS NS NS 1 NS NS NS

010 (Mn-54) 1955–1957, 1960, 1963–1965 2 NS NS NS NS NS NS NS NS 1 NS NS

000 (Fe-55) 1955–1956, 1959–1966, 1980–1986 NS NS NS NS NS NS NS NS NS NS 5 NS

000 (Co-57) 1955–1957, 1964, 1972–1976 NS NS 2 NS NS NS NS NS NS NS NS NS

000 (Ga-66/67) 1958–1959, 1969–1978, 1983 NS NS NS NS NS 5 NS NS NS NS NS NS

000 (Ga-67) 1958–1959, 1969–1978, 1983 NS NS NS 2 NS NS 1 NS NS NS NS NS

SR5 (Sr-85) 1955, 1957–1967, 1970, 1986 3 NS NS NS NS NS NS NS NS NS NS 8

000 (Ru-103) 1955–1957, 1959–1986 NS NS 2 NS NS NS NS NS NS NS NS NS

000 (Ru-103/106) 1955–1957, 1959–1986 NS NS NS NS 4 NS NS NS NS NS NS NS

000 (Cd-109) 1957–1958, 1960–1961, 1963–1966, 1972 NS NS NS NS NS NS NS 1 NS NS NS NS

a. NS = No samples collected.
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 45 of 132

 

8.0 SUMMARY

ORNL isotope production involved a wide array of radioactive materials it termed exotics. NIOSH 

developed an ORNL radionuclide inventory by reviewing shipping records, sales reports, and selected 

logbooks. This inventory was compared to available bioassay data and available bioassay methods. 

This study did not evaluate if ORNL workers were properly monitored but rather if bioassay 

technology deficiencies existed that would result in improper monitoring. 

The ORAU Team compared the available bioassay date from the ORNL internal monitoring database 

with the data provided by ORNL as contained within Energy Employee Occupational Illness 

Compensation Program Act claimant files. With the exception of gross beta analysis (results of which 

seem to be missing from the ORNL database between 1955 and 1959), the sample frequency in the 

ORNL and NOCTS datasets are comparable, although the NOCTS data files tend to be more 

complete. The results are consistent with the conclusion of the ORNL Internal Dosimetry staff that the 

database is incomplete and might be missing up to 25% of the bioassay samples [ORAUT 2013], 

albeit comparison between NOCTS and the ORNL database indicates a slightly lower value based on 

the qualitative evaluation in this document.

Exotics that ORNL HP could not readily detect by gross alpha or beta/gamma methods would have 

presented a particular monitoring challenge. This report identifies 28 radionuclides that might have 

presented such a monitoring challenge. Evaluation of the ORNL HP bioassay program confirmed the 

ability of ORNL Staff to develop specialized bioassay methods as needed to adapt to changing 

conditions and emergent situations. Although no monitoring evidence has been found for the 

28 identified nuclides, it remains clear that ORNL Staff had the capability for developing methods had 

they become necessary. The combination of the inventory and radiological dose coefficients for these 

28 radionuclides allowed the development of bounding potential intakes (see Table 7-6) for these 

radionuclides. These bounding intakes could be used as the basis for a plausible estimation of dose 

from these radionuclides.
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 46 of 132

 

REFERENCES

Arthur DE [1962]. ORNL HP unclassified notebook A-2823. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Nuclear Company. [SRDB Ref ID: 193234] 

Beauchamp EE, ed. [1963]. Isotopes Development Center progress report radioactive source 

development October 1962 - January 1963. Oak Ridge National Laboratory, Oak Ridge, TN: Union 

Carbide Corporation. ORNL-TM-513, April 15. [SRDB Ref ID: 123029]

Brown PE, Davis DM, Henley LC [1957]. A current review of body fluid analysis, procedures, and 

method of reporting - January 1957. Memorandum to distribution. Oak Ridge National Laboratory, 

Oak Ridge, TN: Union Carbide Corporation. August 1. [SRDB Ref ID: 8544]

Burnett THJ [1948]. Report for radiation survey-monitoring section, week ending October 17, 1948. 

Oak Ridge National Laboratory, Oak Ridge, TN: Carbide and Carbon Chemicals Corporation. 

October 19. [SRDB Ref ID: 116212]

Burden J [1961]. ORNL HP unclassified notebook A-2413. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193243] 

Burrell BC [1962a]. ORNL HP unclassified notebook A-2816. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193223] 

Burrell BC [1962b]. ORNL HP unclassified notebook A-2883. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193224] 

Burrell BC [1967]. ORNL HP unclassified notebook A-5033. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193226] 

Butler AC [1962a]. ORNL HP unclassified notebook A-2619. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193244] 

Butler AC [1962b]. ORNL HP unclassified notebook A-2792. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193246] 

Butler AC [1967]. ORNL HP unclassified notebook A-5093. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193238] 

Butler AC [1968]. ORNL HP unclassified notebook A-5371. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193261] 

Butler AC [1969]. ORNL HP unclassified notebook A-5968. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193247] 

Butler HM [1962]. ORNL HP unclassified notebook A-2779. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193253] 

Butler TA [1962]. ORNL HP unclassified notebook A-2641. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193245] 

Cain GC [1956]. ORNL HP unclassified notebook A-0830. Oak Ridge National Laboratory, Oak Ridge, 

TN: Union Carbide Corporation. [SRDB Ref ID: 193259] 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 47 of 132

 

Carver M, Slater M [1994]. Architectural/historical assessment of the Oak Ridge National Laboratory, 

Oak Ridge Reservation, Anderson and Roane counties, Tennessee. Oak Ridge National Laboratory, 

Oak Ridge, TN: Martin Marietta Energy Systems. ORNL/M-3244, January. [SRDB Ref ID: 129205]

Clark RL [1963]. ORNL HP unclassified notebook A-3060. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193229] 

Coleman RE [1963a]. ORNL HP unclassified notebook A-3287. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193230] 

Coleman RE [1963b]. ORNL HP unclassified notebook A-3288. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193231] 

Coleman RE [1963c]. ORNL HP unclassified notebook A-3291. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193232] 

Coleman RE [1964]. ORNL HP unclassified notebook A-3498. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193233] 

Davis DM, Warden AD [1954]. Review of urinalysis program. Memorandum to J.C. Hart. Oak Ridge 

National Laboratory, Oak Ridge, TN: Carbide and Carbon Chemicals Company. November 3. [SRDB 

Ref ID: 109515]

Davis JC [1961]. ORNL HP unclassified notebook A-2575. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193250] 

Davis JC [1962]. ORNL HP unclassified notebook A-2811. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193251] 

Eckerman KF, Sjoreen AL [2006]. Radiological Toolbox user’s manual. Oak Ridge National 

Laboratory, Oak Ridge, TN: UT-Battelle. ORNL/TM-2004/27R1, August 31. [SRDB Ref ID: 151914]

Farabee LB [1946]. Procedure for the determination of plutonium in human urine. Clinton 

Laboratories, Oak Ridge, TN: Monsanto Chemical Company. August 27. [SRDB Ref ID: 114403]

Farabee LB [1947]. Procedure for the determination of plutonium in human urine. Clinton 

Laboratories, Oak Ridge, TN: AEC. MonH-218, April 11. [SRDB Ref ID: 116370]

Farabee LB [1948a]. Analysis of urine specimens for plutonium, uranium, and total beta activity. 

Memorandum to K.Z. Morgan et al. Oak Ridge National Laboratory, Oak Ridge, TN: Union Carbide 

and Carbon Company. November 8. [SRDB Ref ID: 90617]

Farabee LB [1948b]. Analysis of urine and blood samples for radium. Oak Ridge National Laboratory, 

Oak Ridge, TN: Union Carbide and Carbon Company. December 28. [SRDB Ref ID: 90616]

Farabee LB [1955]. Procedure for the radiochemical analysis of strontium and barium in human urine. 

Oak Ridge National Laboratory, Oak Ridge, TN: Carbide and Carbon Chemicals Company. 

ORNL-1932, September 8. [SRDB Ref ID: 121879]

Golden CA [1966]. ORNL HP unclassified notebook A-4612. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 194699] 

Golden CA [1970]. ORNL HP unclassified notebook A-6181. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193248] 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 48 of 132

 

Guinn CR [1968]. ORNL HP unclassified notebook A-5594. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193227] 

Guinn CR [1970]. ORNL HP unclassified notebook A-6154. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193228] 

Hart JC [1950]. Procedure for collection of urine specimens. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide and Carbon Corporation. June 3. [SRDB Ref ID: 109788]

Hart JC [1960]. Applied health physics annual report for 1958. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. ORNL-2777, November 11. [SRDB Ref ID: 21780]

Hart JC, ed. [1963]. Applied health physics annual report for 1962. Oak Ridge National Laboratory, 

Oak Ridge, TN: Union Carbide Corporation. ORNL-3490, September 25. [SRDB Ref ID: 12093]

Hart JC, ed. [1964]. Applied health physics annual report for 1963. Oak Ridge National Laboratory, 

Oak Ridge, TN: Union Carbide Corporation. ORNL-3665, August. [SRDB Ref ID: 12092]

Henley LC [1968]. Health physics and safety bio-assay procedures, CF 68-1-67. Memorandum to J. 

Schacter. Oak Ridge National Laboratory, Oak Ridge, TN: Union Carbide Corporation. March 27. 

[SRDB Ref ID: 114464]

Henley LC [1978]. Radiochemical procedures. Oak Ridge National Laboratory, Oak Ridge, TN: Union 

Carbide Corporation. ORNL/TM-6372, May. [SRDB Ref ID: 861]

Henley LC [no date]. Determination of protactinium in urine. Oak Ridge National Laboratory, Oak 

Ridge, TN. [SRDB Ref ID: 117385]

Hickey EE, Stoetzel GA, Strom DJ, Cicotte GR, Wiblin CM, McGuire SA [1993]. Air sampling in the 

workplace, final report. Washington, DC: U.S. Nuclear Regulatory Commission, Office of Nuclear 

Regulatory Research. NUREG-1400, September. [SRDB Ref ID: 20129]

Hill G [1962a]. ORNL HP unclassified notebook A-2709. Oak Ridge National Laboratory, Oak Ridge, 

TN: Union Carbide Corporation. [SRDB Ref ID: 193252] 

Hill G [1962b]. ORNL HP unclassified notebook A-2907. Oak Ridge National Laboratory, Oak Ridge, 

TN: Union Carbide Corporation. [SRDB Ref ID: 193254] 

Hill G [1969]. ORNL HP unclassified notebook A-5947. Oak Ridge National Laboratory, Oak Ridge, 

TN: Union Carbide Corporation. [SRDB Ref ID: 193255] 

ICRP [1979]. ICRP 30 Part 1 - Limits for intakes of radionuclides by workers. ICRP Publication 30, 

Part I. Ann ICRP 2(3-4). [SRDB Ref ID: 29220]

ICRP [1983]. ICRP 38 - Radionuclide transformations energy and intensity of emissions. ICRP 

Publication 38. Ann ICRP 11–13. [SRDB Ref ID: 190713]

ICRP [1994]. ICRP 68 - Dose coefficients for intakes of radionuclides by workers. ICRP Publication 

68. Ann ICRP 24(4). [SRDB Ref ID: 22731]

Keny RE [1965]. ORNL HP unclassified notebook A-4062. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193249] 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 49 of 132

 

Miller CH [1965]. ORNL HP unclassified notebook A-3909. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193235] 

Miller CH [1967]. ORNL HP unclassified notebook A-5128. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193236] 

Miller CH [1969]. ORNL HP unclassified notebook A-5685. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193237] 

Millspaugh RE [1963]. ORNL HP unclassified notebook A-3282. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193241] 

Millspaugh RE [1964]. ORNL HP unclassified notebook A-3462. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193242] 

MMES [1986]. The ORNL surplus facilities management program maintenance and surveillance plan 

for FY1984. Oak Ridge National Laboratory, Oak Ridge, TN: Martin Marietta Energy Systems. 

ORNL/TM-10268, October. [SRDB Ref ID: 32221]

MMES [1995]. Work plan for the isotopes facilities deactivation project at Oak Ridge National 

Laboratory. Oak Ridge National Laboratory, Oak Ridge, TN: Martin Marietta Energy Systems. 

ORNL/ER-249/R1, May. [SRDB Ref ID: 31777] 

Moore FL [1964]. ORNL HP unclassified notebook A-3470. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 136160]

Morgan KZ, Western F [1949]. Health physics division quarterly report for period ending February 28, 

1949. Oak Ridge National Laboratory, Oak Ridge, TN: Carbide and Carbon Chemicals Corporation. 

ORNL-346, May 19. [SRDB Ref ID: 190572] 

Morgan KZ, Western F [1950]. Health physics division quarterly progress report for period ending 

April 15, 1950. Oak Ridge National Laboratory, Oak Ridge, TN: Union Carbide and Carbon 

Corporation. ORNL-695, May 26. [SRDB Ref ID: 10088]

Morgan KZ [1951]. Health physics division quarterly progress report for period ending July 20, 1951. 

Oak Ridge National Laboratory, Oak Ridge, TN: Carbide and Carbon Chemicals Company. 

ORNL-1086, November 6. [SRDB Ref ID: 10763]

Morgan KZ, Western F [1951]. Health physics division quarterly progress report for period ending 

April 20, 1951. Oak Ridge National Laboratory, Oak Ridge, TN: Carbide and Carbon Chemicals 

Company. ORNL-1004, May 31. [SRDB Ref ID: 10086]

Morgan KZ [1956]. Health physics division semiannual progress report for period ending July 31, 

1956. Oak Ridge National Laboratory, Oak Ridge, TN: Union Carbide Nuclear Company. ORNL-2151,

October 18. [SRDB Ref ID: 10783]

Morgan KZ [1961]. Health physics division annual progress report for period ending July 31, 1961. 

Oak Ridge National Laboratory, Oak Ridge, TN: Union Carbide Corporation. ORNL-3189, October 24. 

[SRDB Ref ID: 11564]

Morgan KZ [1962]. Health physics division annual progress report for period ending July 31, 1962. 

Oak Ridge National Laboratory, Oak Ridge, TN: Union Carbide Corporation. ORNL-3347, 

November 2. [SRDB Ref ID: 97551]
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 50 of 132

 

Morgan KZ, Snyder WS, Struxness EG [1964]. Health physics division annual progress report for 

period ending July 31, 1964. Oak Ridge National Laboratory, Oak Ridge, TN: Union Carbide 

Corporation. ORNL-3697, October. [SRDB Ref ID: 11566]

Morgan KZ, Snyder WS, Struxness EG [1965]. Health physics division annual progress report for 

period ending July 31, 1965. Oak Ridge National Laboratory, Oak Ridge, TN: Union Carbide 

Corporation. ORNL-3849, October. [SRDB Ref ID: 11567]

Morgan KZ, Snyder WS, Struxness EG [1966]. Health physics division annual progress report for 

period ending July 31, 1966. Oak Ridge National Laboratory, Oak Ridge, TN: Union Carbide 

Corporation. ORNL-4007, October. [SRDB Ref ID: 11561]

National Nuclear Data Center [no date]. Decay radiation results. Brookhaven National Laboratory, 

Upton, NY: Brookhaven Science Associates. Date accessed March 20, 2018. [SRDB Ref ID: 190574] 

NBS [1959]. NBS Handbook 69 - Maximum permissible body burdens and maximum permissible 

concentrations of radionuclides in air or water for occupational exposure. Washington, DC: U.S. 

Department of Commerce, National Bureau of Standards. NBS Handbook 69, June 5. [SRDB Ref ID: 

167853]

NIOSH [2012]. Special Exposure Cohort petition evaluation report petition SEC-00189 Rev. 0 Oak 

Ridge National Laboratory (X-10) qualified October 11, 2011. Cincinnati, OH: U.S. Department of 

Health and Human Services, Centers for Disease Control and Prevention, National Institute for 

Occupational Safety and Health. SEC-00189 Rev. 0, August 15. [SRDB Ref ID: 119537]

ORAU [no date]. ENSDF decay data in the MIRD (medical internal radiation dose) format for Br-85. 

Oak Ridge, TN: Oak Ridge Associated Universities. Date accessed March 20, 2018. [SRDB Ref ID: 

190573] 

ORAUT [2004]. Documented communication with [redacted] April 9, 2004 on ORNL TBD. Oak Ridge, 

TN: Oak Ridge Associated Universities Team. April 9. [SRDB Ref ID: 121048]

ORAUT [2013]. Documented communication SEC-00189 with [redacted] on ORNL July 9, 2013. Oak 

Ridge, TN: Oak Ridge Associated Universities Team. July 9. [SRDB Ref ID: 126994]

ORAUT [2022a]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Chemical Technology 

Division annual progress report.” Oak Ridge, TN: Oak Ridge Associated Universities Team. [SRDB 

Ref ID: 193354] 

ORAUT [2022b]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Electronuclear Research 

Division annual progress report.” Oak Ridge, TN: Oak Ridge Associated Universities Team. [SRDB 

Ref ID: 193355]

ORAUT [2022c]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Isotope separations 

progress report.” Oak Ridge, TN: Oak Ridge Associated Universities Team. [SRDB Ref ID: 193356] 

ORAUT [2022d]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Isotopes Development 

Center progress report curium program.” Oak Ridge, TN: Oak Ridge Associated Universities Team. 

[SRDB Ref ID: 193357] 

ORAUT [2022e]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Isotopes Development 

Center progress report fission products.” Oak Ridge, TN: Oak Ridge Associated Universities Team. 

[SRDB Ref ID: 193358] 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 51 of 132

 

ORAUT [2022f]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Isotopes Development 

Center progress report isotopes separations.” Oak Ridge, TN: Oak Ridge Associated Universities 

Team. [SRDB Ref ID: 193359] 

ORAUT [2022g]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Isotopes Development 

Center progress report reactor and cyclotron produced isotopes.” Oak Ridge, TN: Oak Ridge 

Associated Universities Team. [SRDB Ref ID: 193360] 

ORAUT [2022h]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Isotopes Development 

Center progress report target development.” Oak Ridge, TN: Oak Ridge Associated Universities 

Team. [SRDB Ref ID: 193361] 

ORAUT [2022i]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Isotopes Division quarterly 

report.” Oak Ridge, TN: Oak Ridge Associated Universities Team. [SRDB Ref ID: 193362] 

ORAUT [2022j]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Isotopes Division research 

and development report.” Oak Ridge, TN: Oak Ridge Associated Universities Team. [SRDB Ref ID: 

193363] 

ORAUT [2022k]. ORAUT-RPRT-0090, Table 6-1 references for row titled “List of radioisotope 

customers with summary of radioisotope shipments.” Oak Ridge, TN: Oak Ridge Associated 

Universities Team. [SRDB Ref ID: 193364]

ORAUT [2022l]. ORAUT-RPRT-0090, Table 6-1 references for row titled “ORNL status and progress 

report.” Oak Ridge, TN: Oak Ridge Associated Universities Team. [SRDB Ref ID: 193365] 

ORAUT [2022m]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Quantity data on 

radioisotopes.” Oak Ridge, TN: Oak Ridge Associated Universities Team. [SRDB Ref ID: 193366] 

ORAUT [2022n]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Radioisotope cost-price 

study.” Oak Ridge, TN: Oak Ridge Associated Universities Team. [SRDB Ref ID: 193367] 

ORAUT [2022o]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Radioisotope Distribution 

Program progress report.” Oak Ridge, TN: Oak Ridge Associated Universities Team. [SRDB Ref ID: 

193368] 

ORAUT [2022p]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Radioisotope inventory.” 

Oak Ridge, TN: Oak Ridge Associated Universities Team. [SRDB Ref ID: 193369] 

ORAUT [2022q]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Radioisotope production 

and process development annual report.” Oak Ridge, TN: Oak Ridge Associated Universities Team. 

[SRDB Ref ID: 193370]

ORAUT [2022r]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Radioisotope Program 

(8000) progress report.” Oak Ridge, TN: Oak Ridge Associated Universities Team. [SRDB Ref ID: 

193371] 

ORAUT [2022s]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Review of Radioisotopes 

Program.” Oak Ridge, TN: Oak Ridge Associated Universities Team. [SRDB Ref ID: 193372] 

ORAUT [2022t]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Stable isotope and heavy 

element inventories.” Oak Ridge, TN: Oak Ridge Associated Universities Team. [SRDB Ref ID: 

193373] 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 52 of 132

 

ORAUT [2022u]. ORAUT-RPRT-0090, Table 6-1 references for row titled “Transuranium Processing 

Plant semiannual report of production, status, and plan.” Oak Ridge, TN: Oak Ridge Associated 

Universities Team. [SRDB Ref ID: 193374] 

Poggenburg JK [1969]. ORNL HP unclassified notebook A-5901. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. October 8. [SRDB Ref ID: 193258] 

Poggenburg JK [1972]. ORNL HP unclassified notebook A-6802. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. December 29. [SRDB Ref ID: 193256] 

Poggenburg JK [1976]. ORNL HP unclassified notebook A-7748. Oak Ridge National Laboratory, Oak

Ridge, TN: Union Carbide Corporation. April 5. [SRDB Ref ID: 193257] 

Rupp AF [1968]. Isotopes Development Center newsletter for December 1967. Memorandum to A.M. 

Weinberg. Oak Ridge National Laboratory, Oak Ridge, TN: Union Carbide Corporation. January 10. 

[SRDB Ref ID: 122966]

Sillyman DL [1967]. ORNL HP unclassified notebook A-5092. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193239] 

Thompson WE [1952]. Oak Ridge National Laboratory research and radioisotope production. Oak 

Ridge National Laboratory, Oak Ridge, TN: Carbide and Carbon Chemicals Company. January. 

[SRDB Ref ID: 79521]

Tompkins PC, Farabee LB, Khym JX [1949]. Biology division procedure for the radiochemical analysis 

of barium, strontium and the rare earths in human urine. Oak Ridge National Laboratory, Oak Ridge, 

TN: Carbide and Carbon Chemicals Corporation. ORNL-368, August 10. [SRDB Ref ID: 112001]

UCC [1961]. Procedures and practices for radiation protection health physics manual. Oak Ridge 

National Laboratory, Oak Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 12323]

UCC [1965]. Applied health physics annual report for 1964. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. ORNL-3820, June. [SRDB Ref ID: 12090]

UCC [1966]. Health physics and safety annual report for 1965. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. ORNL-3969, July. [SRDB Ref ID: 12087]

UCC [1967]. Health physics and safety annual report for 1966. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. ORNL-4146, August. [SRDB Ref ID: 11558]

UCC [1968]. Health physics and safety annual report for 1967. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. ORNL-4286, August. [SRDB Ref ID: 12072]

UCC [1969]. Applied health physics and safety annual report for 1968. Oak Ridge National 

Laboratory, Oak Ridge, TN: Union Carbide Corporation. ORNL-4423, July. [SRDB Ref ID: 12069]

UCC [1970]. Applied health physics and safety annual report for 1969. Oak Ridge National 

Laboratory, Oak Ridge, TN: Union Carbide Corporation. ORNL-4563, August. [SRDB Ref ID: 12066]

UCC [1971]. Applied health physics and safety annual report for 1970. Oak Ridge National 

Laboratory, Oak Ridge, TN: Union Carbide Corporation. ORNL-4690, August. [SRDB Ref ID: 12061]

UCC [1972]. Applied health physics and safety annual report for 1971. Oak Ridge National 

Laboratory, Oak Ridge, TN: Union Carbide Corporation. ORNL-4795, June. [SRDB Ref ID: 22548]
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 53 of 132

 

UCC [1973]. Applied health physics and safety annual report for 1972. Oak Ridge National 

Laboratory, Oak Ridge, TN: Union Carbide Corporation. ORNL-4894, September. [SRDB Ref ID: 

22549]

UCC [1974]. Applied health physics and safety annual report for 1973. Oak Ridge National 

Laboratory, Oak Ridge, TN: Union Carbide Corporation. ORNL-4974, August. [SRDB Ref ID: 13226]

UCC [1975]. Applied health physics and safety annual report for 1974. Oak Ridge National 

Laboratory, Oak Ridge, TN: Union Carbide Corporation. ORNL-5055, August. [SRDB Ref ID: 11555]

UCC [1976]. Applied health physics and safety annual report for 1975. Oak Ridge National 

Laboratory, Oak Ridge, TN: Union Carbide Corporation. ORNL-5169, August. [SRDB Ref ID: 13227]

UCC [1977]. Applied health physics and safety annual report for 1976. Oak Ridge National 

Laboratory, Oak Ridge, TN: Union Carbide Corporation. ORNL-5310, August. [SRDB Ref ID: 13228]

UCC [1978]. Industrial safety and applied health physics annual report for 1977. Oak Ridge National 

Laboratory, Oak Ridge, TN: Union Carbide Corporation. ORNL-5420, June. [SRDB Ref ID: 22550]

UCC [1979]. Industrial safety and applied health physics annual report for 1978. Oak Ridge National 

Laboratory, Oak Ridge, TN: Union Carbide Corporation. ORNL-5543, September. [SRDB Ref ID: 

22551]

UCC [1980]. Industrial safety and applied health physics annual report for 1979. Oak Ridge National 

Laboratory, Oak Ridge, TN: Union Carbide Corporation. ORNL-5663, September. [SRDB Ref ID: 

13229]

UCC [1981]. Industrial safety and applied health physics annual report for 1980. Oak Ridge National 

Laboratory, Oak Ridge, TN: Union Carbide Corporation. ORNL-5821, November. [SRDB Ref ID: 

22552]

UCC [1982]. Industrial Safety and Applied Health Physics Division annual report for 1981. Oak Ridge 

National Laboratory, Oak Ridge, TN: Union Carbide Corporation. ORNL-5859, August. [SRDB Ref ID: 

13224]

UCC [1983]. Industrial Safety and Applied Health Physics Division annual report for 1982. Oak Ridge 

National Laboratory, Oak Ridge, TN: Union Carbide Corporation. ORNL-5962, December. [SRDB Ref 

ID: 13231]

UT-Battelle [2012]. Oak Ridge National Laboratory incidents database. Spreadsheet. Oak Ridge 

National Laboratory, Oak Ridge, TN. [SRDB Ref ID: 107042]

UT-Battelle [2013]. ORNL complete bioassay database. Database. Oak Ridge National Laboratory, 

Oak Ridge, TN. [SRDB Ref ID: 126306]

Wallace KM [1966]. ORNL HP unclassified notebook A-4608. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193240] 

Walters BJ [1965]. ORNL HP unclassified notebook A-3638. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193225] 

Warden AD [1954]. Request for urine specimen. Memorandum. Oak Ridge National Laboratory, Oak 

Ridge, TN: Carbide and Carbon Chemicals Company. March 17. [SRDB Ref ID: 109886]
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 54 of 132

 

Warden AD [1956]. ORNL HP unclassified notebook A-0901. Oak Ridge National Laboratory, Oak 

Ridge, TN: Union Carbide Corporation. [SRDB Ref ID: 193260] 

Watts JR, Barber JM, Biggerstaff JA, Rao GR [1995]. In vivo monitoring technical basis document. 

Oak Ridge National Laboratory, Oak Ridge, TN: Martin Marietta Energy Systems. TB/IDG/WBCL-95-

R0 Rev. 0, August 30. [SRDB Ref ID: 11500]

Western F [1950]. Routine urine analysis for tritium. Letter to J.E. Rose, Argonne National Laboratory. 

Oak Ridge National Laboratory, Oak Ridge, TN: Union Carbide and Carbon Company. May 18. 

[SRDB Ref ID: 114409]
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 55 of 132

 

ATTACHMENT A 

SUMMARY OF IN VITRO BIOASSAY METHODS

TABLE OF CONTENTS

SECTION TITLE PAGE

A.1 Gross Analysis Methods......................................................................................................... 56

A.1.1 Gross Alpha................................................................................................................ 56

A.1.2 Gross Beta ................................................................................................................. 56

A.1.3 Fission Products......................................................................................................... 56

A.1.4 Rare Earth.................................................................................................................. 57

A.1.5 Transplutonium........................................................................................................... 57

A.2 Element-Specific Analysis Methods ....................................................................................... 58

A.2.1 Barium........................................................................................................................ 58

A.2.2 Cesium ....................................................................................................................... 58

A.2.3 Cobalt......................................................................................................................... 58

A.2.4 Neptunium.................................................................................................................. 59

A.2.5 Plutonium ................................................................................................................... 59

A.2.6 Plutonium-241 ............................................................................................................ 59

A.2.7 Polonium .................................................................................................................... 60

A.2.8 Protactinium ............................................................................................................... 60

A.2.9 Radium....................................................................................................................... 60

A.2.10 Strontium.................................................................................................................... 61

A.2.11 Thorium ...................................................................................................................... 61

A.2.12 Tritium ........................................................................................................................ 62

A.2.13 Uranium...................................................................................................................... 62
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 56 of 132

ATTACHMENT A 

SUMMARY OF IN VITRO BIOASSAY METHODS (continued)

A.1 GROSS ANALYSIS METHODS

A.1.1 Gross Alpha

The ORAU Team observed gross alpha bioassays in the dataset as far back as 1951, and found a 

1957 procedure describing gross alpha urinalysis [Brown et al. 1957]. The method includes a bismuth 

phosphate lanthanum fluoride precipitation of the raw urine with the sample dried for alpha counting.

A 1978 gross alpha fecal method describes the following sequence: drying the fecal sample, 

treatment with an acid solution, separation using ion exchange resins, evaporation of the final product, 

and electrodepositing of the sample for alpha counting [Henley 1978]. 

A.1.2 Gross Beta

Gross beta bioassays were observed in the dataset from as far back as 1954, but reports indicate that 

gross beta urine measurements were performed as early as 1948.

The first instance of a basic procedure for gross beta urinalysis was indicated in a 1948 memorandum 

[Farabee 1948a]. During the procedure, a 50-mL urine sample was taken, the organic material was 

destroyed, the inorganic residue was deposited on a watch glass, and the total activity was 

determined. A note states that some of the activity may be due to potassium being present.

The first more-comprehensive procedure for gross beta urinalysis was issued in 1968 [Henley 1968]. 

This method was used to estimate the beta activity in urine exclusive of the naturally occurring 40K.

Two alternative methods were identified: (1) a precipitation using calcium phosphate, or (2) a nitric 

acid and hydrogen peroxide solution. Both methods involve transferring the precipitate to a betacounting planchet, drying, and beta-counting.

Changes in the process occurred in 1978, based on either a precipitation using a nitric acid 

phosphoric acid solution or a nitric acid and ruthenium carrier solution. Both methods indicate 

transferring the precipitate to a beta-counting planchet, drying, and beta-counting [Henley 1978]. 

Note: Adjustment of results based on the beta emission energy for a specific radionuclide may be 

necessary when the emission energy for the suspected radionuclide is sufficiently different than the 

emission energy for the calibration source. Henley reported that gross beta counting systems were 

calibrated using Sr-90 [Henley 1978, p. 65].

A.1.3 Fission Products

Fission product bioassays were observed in the dataset from as far back as 1951, but reports indicate 

that a procedure for strontium urine measurements was in place as early as 1949 [Tompkins et al.

1949]. A total of 17 fission product urine samples were in the dataset through 1958. The ORAU Team

found no official fission product procedure for this period, but it appears that a rare-earth and alkalineearth procedure might have been used for fission products based on process knowledge of the target 

radionuclide; this procedure is discussed in the next section.

Note: Adjustment of results based on the beta emission energy for a specific radionuclide may be 

necessary when the emission energy for the suspected radionuclide is sufficiently different than the 

emission energy for the calibration source. Henley reported that gross beta counting systems were 

calibrated using Sr-90 [Henley 1978, p. 65].
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 57 of 132

ATTACHMENT A 

SUMMARY OF IN VITRO BIOASSAY METHODS (continued)

A.1.4 Rare Earth

Rare-earth elements include the 15 lanthanides as well as scandium and yttrium. The lanthanides 

include cerium, dysprosium, erbium, europium, gadolinium, holmium, lanthanum, lutetium, 

neodymium, praseodymium, promethium, samarium, terbium, thulium, and ytterbium. Rare-earth 

bioassays were observed in the dataset as far back as 1951, but reports indicate that a procedure for 

rare-earth urine measurements was in place as early as 1949.

The first basic procedure for rare- and alkaline-earth element urinalysis was issued in 1949 [Tompkins

et al. 1949]. The method describes a coprecipitation of the rare- and alkaline-earth elements with 

calcium phosphate from an alkaline solution, separation of the phosphoric acid from the cations by ion 

exchange, and finally a separation of barium, strontium, and rare-earth elements from calcium and 

magnesium by a chromate precipitation. The final precipitate was filtered on a medium porosity glass 

filter, dried, and counted in a standard beta/gamma counting chamber.

The ORAU Team observed changes in the process based on a procedure issued in 1968 [Henley 

1968]. This method was based on a precipitation from an acid solution of ashed urine salts as the 

oxalate. The oxalate was oxidized using perchloric acid and sodium bromate. The precipitate was 

then transferred to a beta-counting planchet, dried, and beta-counted.

Rare-earth fecal (RF0) sampling was performed beginning as early as 1955. Seventy rare-earth fecal 

samples were in the dataset through 1972. No method could be identified.

Note: Adjustment of results based on the beta emission energy for a specific radionuclide may be 

necessary when the emission energy for the suspected radionuclide is sufficiently different than the 

emission energy for the calibration source. Henley reported that gross beta counting systems were 

calibrated using Sr-90 [Henley 1978, p. 65].

A.1.5 Transplutonium

Transplutonium urine bioassays were observed from as far back as 1958. The first procedure for 

transplutonium urinalysis was issued in 1968 [Henley 1968]. The method was improved by performing 

transplutonium separation using ion-exchange methods with neptunium elution using hydrochloric 

acid. The sample was then eluted, evaporated, and alpha-counted.

Two methods were identified from 1978 based on (1) extraction chromatography, or (2) bismuth 

phosphate ion exchange [Henley 1978]. Both methods involve transferring the precipitate to a 

stainless-steel counting disk, drying, and alpha-counting.

The extraction chromatography method used an extraction column to extract the actinide and 

lanthanide elements. The basic phosphate precipitate was eluted with a nitric acid and aluminum 

phosphate solution and passed through an extraction column. The solution was then transferred to a 

watch glass, dried, and alpha-counted.

The bismuth phosphate method uses a basic phosphate precipitate or a hydrochloric acid effluent 

from an ion exchange column. After the plutonium, uranium, neptunium, and protactinium were 

removed from the basic phosphate precipitate by ion exchange, the column effluent would contain any 

trivalent actinides. A rare-earth carrier and hydrofluoric acid were added. The precipitate was then 

transferred to a stainless-steel disk, dried, and alpha-counted.
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 58 of 132

ATTACHMENT A 

SUMMARY OF IN VITRO BIOASSAY METHODS (continued)

The fecal sample method identified from 1978 involved drying the fecal sample, treatment with an acid 

solution, separation using ion exchange resins, evaporation of the final product, and deposit of the 

sample for alpha-counting [Henley 1978]. 

A.2 ELEMENT-SPECIFIC ANALYSIS METHODS

A.2.1 Barium

One barium-specific bioassay was observed in the dataset in 1961, but reports indicate that a 

procedure for barium and the rare-earth elements was in place as early as 1949 [Tompkins et al.

1949]. The method involved a coprecipitation of the rare- and alkaline-earth elements with calcium 

phosphate from an alkaline solution, separation of the phosphoric acid from the cations by ion 

exchange, and finally a separation of barium, strontium, and rare-earth elements from calcium and 

magnesium by a chromate precipitation. The final precipitate was filtered on a medium-porosity glass

filter, dried, and counted in a standard beta/gamma counting chamber.

The ORAU Team observed that changes in the process occurred in 1955 based on ion exchange and 

the eluting of strontium and barium with nitric acid. The final precipitate was deposited to a counting 

dish, dried, and counted in a standard beta/gamma counting chamber. This method was used for both 

barium and strontium analysis [Farabee 1955; Brown et al. 1957]. 

Process improvements occurred in 1968 and again in 1978 based on ion exchange and the eluting of 

strontium and barium with nitric acid. The final precipitate was deposited to a counting dish, dried, and 

counted in a standard beta/gamma counting chamber. It was noted that this method was used for 

both 89Sr and 90Sr in urine. Residue was deposited, dried, and beta-counted in a low-background 

counter. If the presence of radiobarium and radium was suspected, identification could be made by 

spectral analysis [Henley 1968, 1978]. 

A.2.2 Cesium

Cesium bioassays were observed in the dataset from as far back as 1955, and reports indicate that a 

procedure for cesium urine measurements was in place as early as 1956 [Morgan 1956]. A total of 

1,873 cesium urine samples are in the dataset through 1988. In this method, cesium (along with 

potassium) was precipitated from a dilute acid solution as a cobalt nitrite. This precipitate was 

dissolved in nitric acid and a cesium phosphotungstate precipitation separated the cesium from 

potassium. The cesium was finally precipitated for counting. The precipitate was then transferred to a 

counting planchet, dried, and beta-counted.

A 1968 report describes a method in which cesium (along with potassium) was precipitated from a 

dilute acid solution [Henley 1968]. A 1978 report describes a method in which cesium (along with 

potassium) was precipitated from a dilute acid solution as a cobalt nitrite [Henley 1978]. The 1978 

method remained mostly the same as the 1968 method.

A.2.3 Cobalt

Cobalt bioassays were observed in the dataset from as far back as 1954. The first basic procedure for 

cobalt urinalysis was issued in 1968 [Henley 1968]. In concentrations of 6-molar HCl, cobalt ions 

formed a complex of sufficient strength to be absorbed by ion exchange resins. Then the cobalt was 

eluted with HCl, dried, and beta-counted. A 1978 report describes a cobalt urine method that was 

mostly the same as the 1968 method [Henley 1978]. 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 59 of 132

ATTACHMENT A 

SUMMARY OF IN VITRO BIOASSAY METHODS (continued)

A.2.4 Neptunium

Neptunium bioassays were observed from as far back as 1962. A total of 64 neptunium-specific urine 

samples were in the dataset through 1979, although neptunium might also have been measured using 

the gross alpha procedure.

The first procedure for neptunium urinalysis was issued in 1968 [Henley 1968]. The method was 

improved by performing neptunium separation using ion exchange methods with neptunium elution 

using HCl. The sample was then eluted, evaporated, electrodeposited, and alpha-counted. 

The 1978 neptunium fecal method involved drying of the fecal sample, treatment with an acid solution, 

separation using ion exchange resins, evaporation of the final product, and electrodeposit of the 

sample for alpha-counting [Henley 1978]. 

Gross alpha fecal sampling was performed, possibly for neptunium, beginning as early as 1955.

A.2.5 Plutonium

The first procedure for plutonium urinalysis at ORNL was implemented in 1946. The method involved 

precipitating bismuth phosphate from urine, dissolving the precipitate, reprecipitating bismuth 

phosphate, oxidizing the organic matter, and finally precipitating LaF3. The sample was then 

deposited on a platinum disk, dried, and alpha-counted [Farabee 1946]. 

In 1947, the method improved but remained mostly the same as the 1946 method [Farabee 1947]. 

In January 1957, a method was described that involved using a precipitation of calcium oxalate from 

urine, oxidation of the organic matter, and a final LaF3 precipitation [Brown et al. 1957]. The sample 

was deposited on a platinum disk, dried, and alpha-counted.

In 1968, the method was improved by performing plutonium separation using ion exchange methods 

with plutonium elution using HCl [Henley 1968]. The sample was then eluted, evaporated, and 

electrodeposited for counting.

Plutonium-specific fecal sampling was performed beginning in 1968. The fecal sample method 

identified in 1978 involved drying the fecal sample, treatment with an acid solution, separation using 

ion exchange resins, evaporation of the final product, and electrodeposit of the sample for alphacounting [Henley 1978]. 

A.2.6 Plutonium-241

The first basic procedure for 241Pu urinalysis was issued in 1957 [Henley 1968]. This method was 

based on urine samples that were treated with HCl. The plutonium, neptunium, uranium, protactinium, 

and transplutonium elements were adsorbed on an anion exchange resin column. The plutonium was 

eluted from the column with HCl and transferred to a glass cylinder. Toluene was added to the sample 

and then counted for low-energy beta using a liquid scintillation counter.

Another report [Henley 1978] describes another method from 1978. This method was based on urine 

samples that were treated with HCl. The plutonium elements were adsorbed on an anion exchange 

resin column. The plutonium was eluted from the column with HCl and transferred to a glass cylinder.
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 60 of 132

ATTACHMENT A 

SUMMARY OF IN VITRO BIOASSAY METHODS (continued)

Toluene was added to the sample and the counted for low-energy beta using a liquid scintillation 

counter. The method remained mostly the same as the 1968 method.

A.2.7 Polonium

The first basic procedure for polonium urinalysis was issued in 1957 [Brown et al. 1957]. This method 

was based on urine samples treated with HCl and the polonium plated onto clean copper disks 

suspended in the solution for 2 hours. Deposition of the polonium was done by electrolysis. The alpha 

activity was determined by counting both sides of the disks.

Another report describes a method in which polonium was quantitatively deposited on a nickel disk 

from HCl [Henley 1968]. The salt of the ashed urine sample was dissolved in a dichloric acid and a 

clean nickel disk was suspended in the solution for 2 hours. Deposition of the polonium was by 

electrolysis. The alpha activity was determined by counting both sides of the disks.

Another report [Henley 1978] describes a method in which the polonium was quantitatively deposited 

on a nickel disk from HCl. The salt of the ashed urine sample was dissolved in a dichloric acid and a 

clean nickel disk was suspended in the solution for 2 hours. Deposition of the polonium was by 

electrolysis. The alpha activity was determined by counting both sides of the disks. The method 

remained mostly the same as the 1968 method.

A.2.8 Protactinium

Protactinium bioassays were observed from as far back as 1962. From 1952 to 1975, 189 

protactinium urine samples were in the dataset. Note that protactinium might also have been 

measured using the gross alpha procedure.

The initial method involved an extraction of niobium and protactinium from the raw urine using nitric 

and HCl solutions. A protactinium separation was performed using oxalic acid with the sample 

transferred to a stainless-steel planchet, dried, and beta-counted [Henley, no date]. 

Changes in the process occurred in 1968 [Henley 1968]. The method was improved by performing 

protactinium separation using ion exchange methods with protactinium elution using HCl. The sample 

was then eluted, evaporated, and alpha-counted.

Further changes in the process occurred in 1978 [Henley 1978]. The method included an extraction of 

niobium and protactinium from the raw urine using nitric and hydrochloric acid solutions. A 

protactinium separation was performed using oxalic acid with the sample then transferred to a 

stainless-steel planchet, dried, and beta-counted.

A.2.9 Radium

Radium bioassays were observed in the dataset from as far back as 1954, but reports indicate that a 

procedure for radium urine measurements was in place as early as 1948 [Farabee 1948b]. A total of 

330 radium-in-urine samples were in the dataset from 1954 to 1987.

The first basic procedure for radium urinalysis was issued in 1948 [Farabee 1948b]. The referenced 

method, CH-3534, could not be found, but a beta/gamma counting of the decay products in the urine 

was performed at approximately 12 days of ingrowth, at which time the percent of progeny in 

equilibrium with radium and radon was 88.5%.
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 61 of 132

ATTACHMENT A 

SUMMARY OF IN VITRO BIOASSAY METHODS (continued)

The first basic procedure for radium urinalysis found was issued in 1957. This method involved an 

extraction based on HCl and sulfuric acid solutions. The precipitate was then transferred to a 

lacquered platinum disk, dried, and counted. If the activity was found to be greater than 1 cpm, a 

count was performed at a 1- or 2-day interval to determine which isotope was present [Brown et al.

1957]. 

A.2.10 Strontium

Strontium bioassays were observed in the dataset from as far back as 1951, but reports indicate that 

a procedure for strontium urine measurements was in place as early as 1949 [Tompkins et al. 1949]. 

A report from April 15, 1950, indicates that an analysis procedure for strontium was in use [Morgan 

and Western 1950]. The report notes that the 1949 procedure was in use but recommended a change 

that would separate strontium from calcium and magnesium by a strontium nitrate precipitation using 

a nitric acid solution. The report noted that 18 samples had been assayed for strontium by using this 

procedure.

Another report, from July 20, 1951, indicates that an analysis procedure for strontium was in use 

[Morgan 1951]. The report notes that the procedure was lengthy and included the elements of barium, 

strontium, yttrium, lanthanum, and other rare earths.

Changes in the process occurred in 1955 based on ion exchange and the eluting of strontium and 

barium with nitric acid. The final precipitate was deposited to a counting dish, dried and counted in a 

standard beta/gamma counting chamber. This method was for both barium and strontium analysis 

[Farabee 1955; Brown et al. 1957]. 

Improvements in the process occurred in 1968 based on ion exchange and the eluting of strontium 

and barium with nitric acid. The final precipitate was deposited to a counting dish, dried, and counted 

in a standard beta/gamma counting chamber. It was noted that this method was for both 89Sr and 90Sr 

in urine. Residue was deposited, dried, and beta-counted in a low-background counter. If the 

presence of radiobarium and radium was suspected, identification could be made by spectral analysis 

[Henley 1968]. 

Fecal bioassays specific to 90Sr were observed in the dataset from 1960. The fecal sample method 

identified in 1978 involved drying of the fecal sample, treatment with an acid solution, separation using 

ion exchange resins, evaporation of the final product, and deposition of the sample for beta-counting 

[Henley 1978]. 

A.2.11 Thorium

No thorium-specific fecal sampling was identified. However, gross alpha fecal sampling could have 

been performed for thorium beginning as early as 1955.

One thorium fecal sample method was identified in 1978 [Henley 1978]. It involved drying of the fecal 

sample, treatment with an acid solution, separation using ion exchange resins, evaporation of the final 

product, and electrodeposition of the sample for alpha-counting.
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 62 of 132

ATTACHMENT A 

SUMMARY OF IN VITRO BIOASSAY METHODS (continued)

A.2.12 Tritium

Tritium urine bioassays were observed as far back as 1953. No early tritium method was identified, 

but it is thought that a procedure was used that was based on an Argonne National Laboratory 

method extant around 1950 [Western 1950]. 

The first procedure for tritium urinalysis was issued in 1968 [Henley 1968]. In this method, tritium 

samples were counted by liquid scintillation. Urine samples were analyzed by either distilling the 

sample and counting a portion of the distillate for tritium beta, or by adding the raw urine directly to the 

scintillation mix.

Another method for tritium urinalysis was issued in 1978 [Henley 1978]. The method remained mostly 

the same as the 1968 method.

A.2.13 Uranium

Uranium bioassays were observed from as far back as 1949. A total of 15,100 uranium urine samples 

were in the dataset from 1949 through 1988. Only basic information is available for the methods used 

from 1947 to 1949. In 1949, a procedure was developed that describes the separation and elution for 

uranium [Morgan and Western 1949]. The sample was transferred to a platinum plate, evaporated, 

and counted on a standard alpha counter. The overall recovery of 80% to 85% was typical for 233U. In 

1951, improvements were be developed to minimize the time necessary to complete the procedure 

[Morgan and Western 1951]. 

In January 1957, a method using tributyl phosphate in hexane was in use [Brown et al. 1957]. In this 

method, the uranium was separated, transferred to a stainless-steel disk, dried, and alpha-counted.

In 1968, the method was improved by performing uranium separation using ion exchange methods 

with uranium elution using HCl [Henley 1968]. The sample was then eluted, evaporated, and 

electrodeposited for counting.

Gross alpha fecal sampling was performed for uranium beginning as early as 1955. The fecal sample 

method (from 1978) involved drying the fecal sample, treatment with an acid solution, separation 

using ion exchange resins, evaporation of the final product, and electrodeposition of the sample for 

alpha-counting [Henley 1978]. 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 63 of 132

 

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS

The following 179 radionuclides required no further analysis to determine there is no infeasibility in 

respect to ORNL’s monitoring capabilities. Nuclear decay information was generally obtained from the

ICRP Publication 38 [ICRP 1983] nuclear decay data contained within the Radiological Toolbox

[Eckerman and Shoreen 2006]. Nuclear decay information for Br-85 and Es-252 were obtained from 

the National Nuclear Data Center (NuDat) dataset [National Nuclear Data Center, no date; ORAU

2000] as these radionuclides are not in ICRP Publication 38. 

Americium-241

• Production years: 1959–1988

• Half-life: 432 yr

• Decay mode: α

• Progeny: Np-237

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,440 13.0%

alpha 5,490 84.7%

gamma 59.5 35.9%

• Bioassay method: transplutonium (TP0) in urine, GF0 (gross alpha fecal)

Americium-243

• Production years: 1961–1978, 1980–1986, 1988

• Half-life: 7,370 yr

• Decay mode: α

• Progeny: Np-239

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,230 11.0%

alpha 5,280 87.6%

gamma 74.7 68.2%

• Bioassay method: transplutonium (TP0) in urine and GF0 (gross alpha fecal)

Antimony-122

• Production years: 1956, 1959–1968, 1971, 1987

• Half-life: 2.7 d

• Decay mode: EC, β- 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 64 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 521 67.2%

beta 771 25.7%

gamma 564 70.7%

• Bioassay method: gross beta (013) then whole body counting

Antimony-124

• Production years: 1955–1957, 1959–1967

• Half-life: 60.2 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 194 52.2%

beta 918 22.4%

gamma 603 98.3%

gamma 723 10.8%

gamma 1,690 47.8%

• Bioassay method: gross beta (013) then whole body counting

Antimony-125

• Production years: 1955–1957, 1959–1966

• Half-life: 2.7 yr

• Decay mode: β- 

• Progeny: stable
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 65 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 24.9 13.4%

beta 34.7 17.9%

beta 86.9 40.4%

beta 215 13.6%

X-ray 27.5 26.6%

gamma 428 29.8%

gamma 463 10.6%

gamma 601 17.8%

gamma 636 11.3%

• Bioassay method: gross beta (013) then whole body counting, Sb-125 specific method (015) 

used in 1962 and 1963, radiation from daughter Te-125m

Argon-37

• Production years: 1955–1957, 1959–1971, 1973–1982

• Half-life: 35.04 d

• Decay mode: EC

• Progeny: stable

• Important energy emissions: NA

• Bioassay method: NA-noble gas: external monitoring is controlling for these materials

Arsenic-71

• Production years: 1960

• Half-life: 65.3 hr

• Decay mode: EC, β+ 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

positron 352 28.0%

gamma 175 82.0%

gamma 511 56.7%

• Bioassay method: gross beta (013)

Arsenic-72

• Production years: 1960
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 66 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Half-life: 26 hr

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

positron 1,120 64.2%

positron 1,530 16.3%

gamma 511 176.0%

gamma 834 79.5%

• Bioassay method: gross beta (013)

Arsenic-74

• Production years: 1957–1959, 1961, 1965

• Half-life: 17.77 d

• Decay mode: EC, β+, β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 243 15.4%

positron 408 26.0%

beta 531 18.6%

gamma 511 58.1%

gamma 596 59.4%

gamma 635 15.4%

• Bioassay method: gross beta (013) then whole body counting

Arsenic-76

• Production years: 1956–1957, 1959–1967

• Half-life: 25.9 hr

• Decay mode: β- 

• Progeny: stable
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 67 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 993 35.3%

beta 1,260 51.1%

gamma 559 45.0%

• Bioassay method: gross beta (013) then whole body counting

Arsenic-77

• Production years: 1956–1957, 1959–1966

• Half-life: 38.8 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 229 97%

• Bioassay method: gross beta (013 and GB0)

Barium-131

• Production years: 1955–1957, 1959–1971

• Half-life: 11.5 d

• Decay mode: EC

• Progeny: Cs-131

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 3.45 79.1%

A.E. 4.17 24.4%

I.C. 87.8 17.9%

gamma 216 19.7%

gamma 373 14.0%

gamma 496 46.8%

• Bioassay method: strontium (SR0)

Barium-135m

• Production years: 1970, 1986

• Half-life: 28.7 hr
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 68 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Decay mode: IT

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

I.C. 231 59.9%

I.C. 262 11.3%

X-ray 31.8 15.5%

X-ray 32.2 28.9%

gamma 268 15.6%

• Bioassay method: in vivo counting

Barium-140

• Production years: 1955–1957, 1959–1968, 1970–1978, 1980–1981, 1983

• Half-life: 12.75 d

• Decay mode: β- 

• Progeny: La-140

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 141 23.9%

beta 344 38.2%

beta 362 24.1%

I.C. 23.7 56.0%

I.C. 28.8 12.9%

gamma 30 14.1%

gamma 537 24.4%

• Bioassay method: strontium (SR0), Ba-140 specific method (014) used one time in 1961

Berkelium-249

• Production years: 1964, 1967, 1969–1984, 1986, 1988

• Half-life: 330 d

• Decay mode: SF, β-, α

• Progeny: Am-245
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 69 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 32.4 100%

• Bioassay method: transplutonium (TPO)

Bismuth-207

• Production years: 1957

• Half-life: 32.9 yr

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 10.4 16.1%

X-ray 73 21.8%

X-ray 75.3 36.6%

gamma 570 97.8%

gamma 1,060 74.6%

• Bioassay method: gross beta (013)

Bismuth-210

• Production years: 1955–1957, 1959–1970

• Half-life: 5.01 d

• Decay mode: β- 

• Progeny: Po-210

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 389 100%

• Bioassay method: gross beta (013 and GB0)

Bromine-82

• Production years: 1956–1967

• Half-life: 35.3 hr

• Decay mode: β- 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 70 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 138 97.0%

gamma 554 70.8%

gamma 619 43.4%

gamma 698 28.5%

gamma 777 83.5%

gamma 828 24.0%

gamma 1,040 27.2%

gamma 1,320 26.5%

gamma 1,470 16.3%

• Bioassay method: gross beta (013), Br-82/Br-83 (008) then whole body counting; Br-82 

specific method used in 1960 and 1961

Bromine-85

• Production year: 1963

• Half-life: 2.9 min

• Decay mode: β- 

• Progeny: Kr-85m

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 1,070 95.7%

• Bioassay method: gross beta

Cadmium-115

• Production years: 1955–1956, 1960, 1962–1966

• Half-life: 53.46 hr

• Decay mode: β- 

• Progeny: In-115m

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 184 33.0%

beta 394 62.5%

gamma 528 27.5%
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 71 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Bioassay method: gross beta (013 and GB0), radiation from daughter In-115m.

Cadmium-115m

• Production years: 1955–1956, 1960–1966

• Half-life: 44.6 d

• Decay mode: β-

• Progeny: In-115

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 618 97%

gamma 934 2%

• Bioassay method: gross beta (013 and GB0), radiation from daughter In-115m

Calcium-45

• Production years: 1955–1966

• Half-life: 162.7 d

• Decay mode: β-

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 77.2 100%

• Bioassay method: gross beta (013 and GB0)

Calcium-47

• Production years: 1960–1984

• Half-life: 4.54 d

• Decay mode: β-

• Progeny: Sc-47

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 243 80.9%

beta 819 19.0%

gamma 1,300 74.6%
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 72 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Bioassay method: gross beta (013) then whole body counting, radiation from daughter Sc-47

Californium-248

• Production years: 1972

• Half-life: 334 d

• Decay mode: SF, α

• Progeny: Cm-244

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 6,220 19.6%

alpha 6,260 80.0%

• Bioassay method: transplutonium (TP0)

Californium-249

• Production years: 1968–1976, 1979–1982, 1984, 1986

• Half-life: 351 yr

• Decay mode: SF, α

• Progeny: Cm-245

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,810 82.4%

I.C. 31.0 13.6%

I.C. 35.8 10.5%

gamma 333 14.6%

gamma 388 66.0%

• Bioassay method: transplutonium (TP0)

Californium-250

• Production years: 1970, 1973–1976, 1980

• Half-life: 13.08 yr

• Decay mode: SF, α

• Progeny: Cm-246
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 73 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,990 15.0%

alpha 6,030 84.6%

• Bioassay method: transplutonium (TP0)

Californium-252

• Production years: 1962, 1967–1988

• Half-life: 2.638 yr

• Decay mode: SF, α

• Progeny: Cm-248

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 6,080 15.2%

alpha 6,120 81.5%

beta 1,280 19.2%

• Bioassay method: transplutonium (TP0) Gross Alpha (GU0), Cf-252 specific method 1989–

1992

Californium-253

• Production years: 1984

• Half-life: 17.81 d

• Decay mode: β-, α

• Progeny: Cm-249, Es-253

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 65.5 49.8%

beta 79.1 49.8%

A.E. 12.3 10.2%

I.C. 19.6 32.9%

• Bioassay method: transplutonium (TP0)

Carbon-11

• Production years: 1975, 1977, 1979–1980

• Half-life: 20.39 min
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 74 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

positron 386 99.8%

gamma 511 200%

• Bioassay method: whole body counting

Carbon-14

• Production years: 1955–1975, 1980–1983, 1985

• Half-life: 5,700 yr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 49.5 100%

• Bioassay method: gross beta (013 and GB0), C-14 specific methods 1986–1992

Cerium-141

• Production years: 1955–1957, 1959–1966, 1970

• Half-life: 32.5 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 130 69.7%

beta 181 30.3%

I.C. 103 18.9%

gamma 145 48.3%

• Bioassay method: rare earths (FU0)

Cerium-144

• Production years: 1955–1979, 1981–1988
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 75 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Half-life: 284.9 d

• Decay mode: β- 

• Progeny: Pr-144m, Pr-144

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 50.3 19.6%

beta 91.3 76.6%

gamma 134 11.1%

• Bioassay method: rare earths (FU0), whole body counting, Ce-144 specific method

Cesium-132

• Production years: 1962

• Half-life: 6.5 d

• Decay mode: EC

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

Gamma 668 97.5

• Bioassay method: nuclide specific method (012), whole body counting

Cesium-134

• Production years: 1955–1957, 1959–1966

• Half-life: 2.06 yr

• Decay mode: EC, β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 23.1 27.3%

beta 210 70.2%

gamma 569 15.4%

gamma 605 97.6%

gamma 796 85.5%

• Bioassay method: gross beta (013) then whole body counting
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 76 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Cesium-137

• Production years: 1955–1988

• Half-life: 30.16 yr

• Decay mode: β- 

• Progeny: Ba-137m

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 174 94.4%

gammaa 662 100.0%

a. See Comments below.

• Bioassay method: Cs-137 specific method (CS7) then whole body counting

• Comments: 662 keV gamma is from daughter Ba-137m

Chlorine-36

• Production years: 1955–1972

• Half-life: 3.01E5 yr

• Decay mode: EC, β+, β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 278 98.1%

• Bioassay method: gross beta (013 and GB0)

Chlorine-38

• Production years: 1956

• Half-life: 37.2 min

• Decay mode: β- 

• Progeny: stable
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 77 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 420 31.9%

beta 1,180 10.5%

beta 2,240 57.6%

gamma 1,640 31.9%

gamma 2,170 42.4%

• Bioassay method: gross beta (013); only production year in pre-existing SEC

Cobalt-56

• Production years: 1967, 1972, 1977 

• Half-life: 77.2 d

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

positron 631 18.1%

gamma 511 38.0%

gamma 847 99.9%

gamma 1,240 66.9%

gamma 1,770 15.5%

gamma 2,600 17.3%

• Bioassay method: whole body counting

Cobalt-58

• Production years: 1955–1957, 1959–1965

• Half-life: 70.86 d

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

positron 201 14.9%

gamma 511 29.8%

gamma 811 99.5%

• Bioassay method: gross beta (013) then whole body counting
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 78 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Cobalt-60

• Production years: 1955–1988

• Half-life: 5.27 yr

• Decay mode: β-

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 95.9 99.9%

gamma 1,170 99.9%

gamma 1,330 100.0%

• Bioassay method: gross beta (013) then whole body counting, Co-60-specific method used in 

1962–1964

Copper-64

• Production years: 1955–1969, 1976

• Half-life: 12.7 hr

• Decay mode: EC, β+, β-

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 190 39.0%

positron 278 17.4%

gamma 511 34.8%

• Bioassay method: gross beta (013 and GB0)

Copper-67

• Production years: 1963–1964, 1967–1968, 1970–1971, 1973–1976

• Half-life: 61.83 hr

• Decay mode: β-

• Progeny: stable
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 79 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 116 56.9%

beta 149 22.0%

beta 184 20.0%

I.C. 83.7 12.1%

gamma 93.3 16.1%

gamma 185 48.7%

• Bioassay method: whole body counting

Curium-242

• Production years: 1962–1966, 1968, 1986

• Half-life: 162.8 d

• Decay mode: SF, α

• Progeny: Pu-238

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 6,070 25.9%

alpha 6,110 74.1%

• Bioassay method: transplutonium (TP0)

Curium-243

• Production years: 1965, 1972–1973, 1975–1976, 1981–1983

• Half-life: 29.1 yr

• Decay mode: α, EC

• Progeny: Pu-239, Am-243
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 80 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,740 11.5%

alpha 5,790 72.6%

A.E. 10.7 28.2%

A.E. 14.2 14.6%

I.C. 106 23.3%

I.C. 155 17.5%

X-ray 18.4 13.8%

X-ray 100 14.7%

X-ray 104 23.3%

gamma 228 10.6%

gamma 278 14.0%

• Bioassay method: transplutonium (TP0)

Curium-244

• Production years: 1962–1964, 1966–1988

• Half-life: 18.1 yr

• Decay mode: SF, α

• Progeny: Pu-240

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,760 23.6%

alpha 5,800 76.4%

• Bioassay method: transplutonium (TP0), Cm-242/244 specific method (CM0) used in 1986–

1988

Curium-245

• Production years: 1969, 1972–1973, 1986

• Half-life: 8,500 yr

• Decay mode: α

• Progeny: Pu-241
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 81 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,362 92.9%

I.C. 52.6 44.6%

X-ray 18.4 11.1%

X-ray 100 21.6%

X-ray 104 34.2%

• Bioassay method: transplutonium (TP0)

Curium-246

• Production years: 1970–1971, 1973, 1977, 1988

• Half-life: 4,760 yr

• Decay mode: SF, α

• Progeny: Pu-242

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,340 17.8%

alpha 5,390 82.2%

• Bioassay method: transplutonium (TP0)

Curium-247

• Production years: 1969, 1972

• Half-life: 1.56E+07 yr

• Decay mode: α

• Progeny: Pu-243

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,870 71.0%

alpha 5,270 13.8%

gamma 402 72.0%

• Bioassay method: transplutonium (TP0)

Curium-248

• Production years: 1968–1980, 1982–1984, 1986, 1988

• Half-life: 3.48E+05 yr
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 82 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Decay mode: SF, α

• Progeny: Pu-244

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,030 16.5%

alpha 5,080 75.0%

beta 1,370 55.9%

gamma 1,100 12.2%

• Bioassay method: transplutonium (TP0)

Dysprosium-157

• Production years: 1975

• Half-life: 8.1 hr

• Decay mode: EC

• Progeny: Tb-157

• Important energy emissions:

Emission type Energy (keV) Abundance

X-ray 43.8 24.2%

X-ray 44.6 43.3%

gamma 326 92.0%

• Bioassay method: rare earth (FU0)

Dysprosium-166 

• Production years: 1965, 1984

• Half-life: 81.6 hr

• Decay mode: β- 

• Progeny: Ho-166

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 118 89.1%

I.C. 18.9 14.1%

I.C. 26.8 54.6%

I.C. 46.2 10.6%

X-ray 46.8 14.8%

X-ray 47.6 26.3%

gamma 82.5 13.8%
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 83 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Bioassay method: rare earth (FU0)

Einsteinium-252

• Production years: 1970

• Half-life: 471.7 d

• Decay mode: α, EC

• Progeny: Bk-248

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 6,562 10.6%

alpha 6,632 62.6%

A.E. 11.2 15.2%

X-ray 15.7 18.8%

gamma 139 11.7%

gamma 785 15.4%

• Bioassay method: gross alpha

Einsteinium-253

• Production years: 1967–1981, 1984, 1986, 1988

• Half-life: 20.47 d

• Decay mode: SF, α

• Progeny: Bk-249

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 6,630 89.8%

• Bioassay method: transplutonium (TP0)

Einsteinium-254

• Production years: 1972–1974, 1980, 1982, 1984, 1988

• Half-life: 275.7 d

• Decay mode: α

• Progeny: Bk-250
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 84 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 6,430 93.4%

A.E. 11.5 43.9%

A.E. 15.4 23.4%

I.C. 10.2 31.7%

I.C. 16.0 16.2%

I.C. 17.3 66.3%

I.C. 30.5 14.9%

I.C. 37.6 18.2%

X-ray 15.3 32.1%

• Bioassay method: transplutonium (TP0)

Erbium-171

• Production years: 1973

• Half-life: 7.52 hr

• Decay mode: β- 

• Progeny: Tm-171

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 362 94.3%

I.C. 52.1 39.5%

gamma 112 20.5%

gamma 296 28.9%

gamma 308 64.4%

• Bioassay method: gross beta (Sr-90) (GB0) as production in years of pre-existing SEC

Europium-152

• Production years: 1962, 1968, 1974–1975, 1978–1981, 1984–1985, 1988

• Half-life: 13.53 yr

• Decay mode: β-, EC, β+

• Progeny: Au-152
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 85 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 222 13.8%

I.C. 74.9 19.4%

X-ray 40.2 38.3%

gamma 122 28.7%

gamma 344 26.6%

gamma 779 13.0%

gamma 964 14.6%

gamma 1,090 10.2%

gamma 1,110 13.7%

gamma 1,410 21.1%

• Bioassay method: whole body counting

Europium-155

• Production years: 1955–1957, 1959–1968, 1975

• Half-life: 4.76 yr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 39.2 46.7%

beta 44.6 24.8%

beta 70.2 17.5%

I.C. 36.2 11.1%

X-ray 43.1 11.8%

gamma 86.5 30.7%

gamma 105 21.2%

• Bioassay method: whole body counting

Fermium-255

• Production years: 1984, 1988

• Half-life: 20.07 hr

• Decay mode: α

• Progeny: Cf-251
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 86 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 7,020 92.5%

A.E. 11.4 36.2%

A.E. 15.4 19.4%

I.C. 17.9 16.0%

I.C. 19.7 31.2%

I.C. 24.8 11.6%

I.C. 32.4 20.4%

I.C. 56.2 20.1%

I.C. 61.5 13.5%

X-ray 15.7 30.1%

X-ray 20.7 15.2%

• Bioassay method: transplutonium (TP0)

Fermium-257

• Production years: 1968–1977, 1980, 1984, 1986, 1988

• Half-life: 100.5 d

• Decay mode: α

• Progeny: Cf-253

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 6,520 92.4%

A.E. 11.8 34.5%

A.E. 15.8 18.5%

I.C. 35.6 34.9%

I.C. 36.4 12.8%

I.C. 43.8 40.8%

I.C. 56.5 14.0%

I.C. 105 14.7%

X-ray 15.7 25.6%

X-ray 20.7 14.9%

X-ray 110 16.4%

X-ray 116 25.3%

gamma 241 11.0%

• Bioassay method: transplutonium (TP0)

Gadolinium-148

• Production years: 1970

• Half-life: 74.6 yr

• Decay mode: α
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 87 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 3,180 100%

• Bioassay method: gross alpha (GA0)

Gadolinium-153

• Production years: 1971, 1973–1988

• Half-life: 240.4 d

• Decay mode: EC

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

I.C. 21.1 11.0%

I.C. 54.6 30.8%

X-ray 40.9 35.0%

X-ray 41.6 63.1%

X-ray 47.1 12.3%

gamma 97.4 29.0%

gamma 103 21.1%

• Bioassay method: rare earth (FU0) then whole body counting

Gallium-68

• Production years: 1971

• Half-life: 67.71 min

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

positron 836 87.7%

gamma 511 178.0%

• Bioassay method: whole body counting

Gallium-72

• Production years: 1955, 1957, 1960–1970
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 88 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Half-life: 14.1 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 22.1 15.0%

beta 22.7 21.7%

beta 346 27.6%

beta 1,360 10.3%

gamma 630 24.8%

gamma 834 95.6%

gamma 2,200 25.9%

gamma 2,510 12.8%

• Bioassay method: gross beta (013 and GB0)

Gold-198

• Production years: 1955, 1957–1966

• Half-life: 2.7 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 314 99.0%

gamma 412 95.6%

• Bioassay method: gross beta (013 and GB0)

Gold-199

• Production years: 1955, 1957, 1959–1967

• Half-life: 3.14 d

• Decay mode: β- 

• Progeny: stable
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 89 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 67.2 21.5%

beta 82.3 72.0%

I.C. 144 10.1%

gamma 158 40.0%

• Bioassay method: gross beta (013) then whole body counting

Hafnium-181

• Production years: most years between 1955, 1957, 1959–1977, 1979–1980

• Half-life: 42.4 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 121 92.5%

I.C. 65.5 21.2%

I.C. 122 12.7%

I.C. 123 10.5%

X-ray 57.7 16.0%

gamma 133 43.3%

gamma 346 15.1%

gamma 482 80.5%

• Bioassay method: gross beta (013 and GB0) then whole body counting

Holmium-156

• Production years: 1965

• Half-life: 56 min

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

I.C. 83.9 24.1%

gamma 138 51.1%

gamma 266 64.9%

gamma 366 14.3%

gamma 511 86.3%
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 90 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Bioassay method: rare earth (FU0)

Holmium-166

• Production years: 1968

• Half-life: 26.83 hr

• Decay mode: β-

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 651 48.7%

beta 694 50.0%

I.C. 23.0 11.0%

I.C. 71.3 12.7%

I.C. 72.2 13.1%

• Bioassay method: 013 gross beta

Hydrogen-3

• Production years: 1955–1957, 1959–1988

• Half-life: 12.35 yr

• Decay mode: β-

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 5.7 100%

• Bioassay method: HY3

Indium-111

• Production years: 1969–1971, 1973

• Half-life: 2.83 d

• Decay mode: EC

• Progeny: stable
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 91 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 19.3 10.6%

X-ray 23.0 24.0%

X-ray 23.2 45.0%

gamma 171 90.7%

gamma 24.5 94.1%

• Bioassay method: whole body counting

Indium-114

• Production years: 1955–1957, 1959–1977, 1981

• Half Life: 71.9 s

• Decay mode: β-, EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 779 99.4%

• Bioassay method: gross beta (013)

Indium-114m

• Production years: 1975

• Half-life: 49.51 d

• Decay mode: EC, IT

• Progeny: In-114

• Important energy emissions:

Emission type Energy (keV) Abundance

I.C. 162 39.8%

I.C. 186 16.0%

I.C. 187 12.8%

X-ray 24.2 18.3%

gamma 190 15.56%

• Bioassay method: whole body counter

Iodine-123

• Production years: 1965, 1967–1970
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 92 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Half-life: 13.3 hr

• Decay mode: EC

• Progeny: Te-123m, Te-123

• Important energy emissions:

Emission type Energy (keV) Abundance

I.C. 12.7 13.7%

X-ray 27.2 25.0%

X-ray 27.5 46.5%

gamma 159 83.3%

• Bioassay method: thyroid count

Iodine-132

• Production years: 1967–1972

• Half-life: 2.3 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 242 12.9%

beta 422 18.7%

beta 608 12.5%

beta 841 18.9%

gamma 523 16.0%

gamma 630 13.3%

gamma 668 98.7%

gamma 773 75.6%

gamma 955 17.6%

• Bioassay method: thyroid count

Iridium-192

• Production years: 1955–1968, 1970–1971, 1973–1988

• Half-life: 73.8 d

• Decay mode: β-, EC

• Progeny: stable
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 93 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 162 41.4%

beta 210 48.0%

gamma 296 28.7%

gamma 308 29.7%

gamma 317 82.7%

gamma 468 47.8%

• Bioassay method: gross beta (013) then whole body counting

Iridium-194

• Production years: 1959, 1961, 1963, 1968

• Half-life: 19.3 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 846 85.4%

gamma 328 13.1%

• Bioassay method: gross beta (013) then whole body counting

Iron-59

• Production years: 1955–1956, 1958–1967

• Half-life: 44.5 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 81 45.3%

beta 149 53.1%

gamma 1,100 56.5%

gamma 1,290 43.2%

• Bioassay method: gross beta (013 and GB0) then whole body counting, Fe-59 specific method 

(009) used between 1960 and 1964
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 94 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Krypton-85

• Production years: 1955–1988

• Half-life: 10.76 yr

• Decay mode: β-

• Progeny: stable

• Important energy emissions: NA

Emission type Energy (keV) Abundance

beta 252 99.6%

gamma 514 0.4%

• Bioassay method: NA-noble gas: external monitoring is controlling for these materials

Lanthanum-140

• Production years: 1955–1957, 1959–1966, 1987

• Half-life: 1.68 d

• Decay mode: β-

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 442 11.2%

beta 488 45.2%

beta 630 19.7%

gamma 329 20.3%

gamma 487 45.5%

gamma 816 23.3%

gamma 1,600 95.4%

• Bioassay method: rare earth (FU0) and whole body counting

Lead-203

• Production years: 1972–1973

• Half-life: 51.9 hr

• Decay mode: EC

• Progeny: stable
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 95 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 10.1 17.6%

I.C. 193 13.6%

X-ray 71.1 25.8%

X-ray 73.1 43.5%

gamma 279 80.8%

• Bioassay method: whole body counting

Magnesium-28

• Production years: 1966, 1969–1970, 1977, 1983–1984, 1987–1988

• Half-life: 20.91 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 156 94.7%

I.C. 29.1 27.7%

gamma 401 36.6%

gamma 941 38.3%

gamma 1,340 52.6%

• Bioassay method: whole body counting

Manganese-52

• Production years: 1960

• Half-life: 5.59 d

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 242 29.7%

gamma 511 59.3%

gamma 744 90.0%

gamma 936 94.5%

gamma 1,430 100.0%

• Bioassay method: gross beta (013)
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 96 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Mercury-203

• Production years: 1955–1957, 1959–1967

• Half-life: 46.6 d

• Decay mode: β-

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 57.8 100.0%

I.C. 193 13.8%

gamma 279 81.5%

• Bioassay method: gross beta (013) then whole body counting

Molybdenum-99

• Production years: 1957, 1959–1971

• Half-life: 65.9 hr

• Decay mode: β-

• Progeny: Tc-99m, Tc-99

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 133 16.4%

beta 443 82.2%

gamma 740 12.13%

• Bioassay method: gross beta (013) then whole body counting

Neodymium-140

• Production years: 1969

• Half-life: 3.37 d

• Decay mode: EC

• Progeny: Pr-140
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 97 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions: emissions listed include Pr-140 progeny

Emission type Energy (keV) Abundance

X-ray 35.6 21.7%

X-ray 36.1 39.7%

Positron 1,070 51.0%

• Bioassay method: gross beta

Neodymium-147

• Production years: 1955–1957, 1959–1973, 1979

• Half-life: 10.98 d

• Decay mode: β- 

• Progeny: Pm-147

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 106 15.3%

beta 264 80.9%

I.C. 45.9 49.2%

X-ray 38.2 13.3%

X-ray 38.8 24.1%

gamma 91.1 27.9%

gamma 531 13.1%

• Bioassay method: rare earth (FU0)

Neodymium-149

• Production years: 1979

• Half-life: 1.73 hr

• Decay mode: β- 

• Progeny: Pm-149
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 98 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 355 18.6%

beta 403 21.0%

beta 515 17.1%

beta 541 24.1%

I.C. 69.1 17.6%

X-ray 38.8 16.9%

gamma 114 19.2%

gamma 211 25.9%

gamma 270 10.7%

• Bioassay method: rare earth (FU0)

Neptunium-236

• Production years: 1965

• Half-life: 154,000 yr

• Decay mode: EC, β- 

• Progeny: Pu-236, U-236

• Important energy emissions: annihilation photons

Emission type Energy (keV) Abundance

beta 46.4 12.0%

A.E. 103 71.7%

A.E. 13.6 36.5%

I.C. 83.2 34.4%

I.C. 139 22.0%

X-ray 13.6 42.7%

X-ray 17.3 40.8%

X-ray 95.1 20.2%

X-ray 98.9 32.3%

gamma 160 31.5%

• Bioassay method: whole body counting

Neptunium-237

• Production years: 1955–1957, 1959, 1961–1962, 1964–1965, 1967–1968, 1970, 1972–1987

• Half-life: 2.144 E6 yr

• Decay mode: α

• Progeny: Pa-233
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 99 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,770 25.7%

alpha 4,790 48.3%

I.C. 36.7 27.3%

I.C. 40.4 22.9%

I.C. 52.9 14.1%

gamma 29.4 15.0%

gamma 86.5 12.4%

• Bioassay method: gross alpha (GU0) and neptunium (NP0), Np-237 (017)

Neptunium-238

• Production years: 1965–1966

• Half-life: 2.117 d

• Decay mode: β- 

• Progeny: Pu-238

• Important energy emissions: annihilation photons

Emission type Energy (keV) Abundance

beta 72.2 44.8%

beta 412 41.0%

I.C. 21.7 30.9%

I.C. 26.0 26.5%

I.C. 39.5 16.3%

gamma 984 25.2%

gamma 1,030 18.3%

• Bioassay method: gross beta (013 and GB0)

Nickel-63

• Production years: most years 1955–1957, 1959–1972, 1978, 1980, 1985–1987

• Half-life: 100.1 yr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 17.4 100%

• Bioassay method: gross beta (013 and GB0)
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 100 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Nickel-66

• Production years: 1968

• Half-life: 54.6 hr

• Decay mode: β-

• Progeny: Cu-66

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 73.4 100%

• Bioassay method: gross beta (GB0)

Niobium-90

• Production years: 1957

• Half-life: 14.6 hr

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 662 53.7%

I.C. 123 18.0%

gamma 511 107.0%

gamma 1,130 92.7%

gamma 2,320 82.0%

• Bioassay method: gross beta (013)

Niobium-92

• Production years: 1963

• Half-life: 3.47 E+7 yr

• Decay mode: EC

• Progeny: stable

• Important energy emissions: annihilation photons
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 101 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

A.G. 13.3 16.4%

gamma 561 100.0%

gamma 935 100.0%

• Bioassay method: whole body counting

Niobium-92m

• Production years: 1967

• Half-life: 10.15 d

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 13.3 17.1%

gamma 934 99.1%

• Bioassay method: whole body counting

Niobium-95

• Production years: 1955–1957, 1959–1981, 1983–1985

• Half-life: 35 d

• Decay mode: β-

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 43.4 100.0%

gamma 766 99.8%

• Bioassay method: gross beta (013), Nb-95 specific method (005 – Zn/Nb95), whole body

counting

Osmium-191

• Production years: 1957, 1959–1970, 1984

• Half-life: 15.4 d

• Decay mode: β-

• Progeny: stable
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 102 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 37.8 100.0%

I.C. 53.1 65.3%

X-ray 63.5 18.2%

X-ray 65.1 31.3%

gamma 129.42 29.0%

• Bioassay method: gross beta (013) and whole body counting

Palladium-109

• Production years: 1957, 1959–1971

• Half-life: 13.7 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 361 99.9%

I.C. 62.6 41.1%

I.C. 84.5 19.3%

I.C. 84.7 22.4%

X-ray 22.1 18.6%

• Bioassay method: gross beta (013 and GB0)

Phosphorus-32

• Production years: 1955–1967

• Half-life: 14.26 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 695 100%

• Bioassay method: P-32 specific method (PH2)

Phosphorus-33

• Production years: 1964–1965, 1967–1987
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 103 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Half-life: 25.3 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 76.4 100

• Bioassay method: gross beta (013 and GB0)

Platinum-195m

• Production years: 1972–1974, 1978

• Half-life: 4.02 d

• Decay mode: IT

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

I.C. 116 17.5%

I.C. 118 40.1%

I.C. 127 19.6%

X-ray 65.3 22.7%

X-ray 67.0 38.8%

gamma 98.85 11.4%

• Bioassay method: whole body counting

Platinum-197

• Production years: 1965

• Half-life: 19.89 hr

• Decay mode: β- 

• Progeny: stable
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 104 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 198 81.2%

beta 225 10.6%

I.C. 63.0 30.7%

I.C. 63.6 14.1%

I.C. 65.4 10.5%

I.C. 74.6 13.5%

gamma 77.4 17.0%

• Bioassay method: whole body scan 

Plutonium-236

• Production years: 1968, 1970, 1973, 1975, 1981, 1984, 1986

• Half-life: 2.86 yr

• Decay mode: SF, α

• Progeny: U-232

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,720 30.6%

alpha 5,770 69.3%

I.C. 26.5 11.9%

I.C. 30.4 10.4%

• Bioassay method: plutonium (PU0)

Plutonium-237

• Production years: 1984, 1986

• Half-life: 45.2 d

• Decay mode: α, EC

• Progeny: U-233, Np-237

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 10.4 28.3%

A.E. 13.9 14.6%

X-ray 97.5 12.4%

X-ray 102 19.8%

• Bioassay method: plutonium (PU0)
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 105 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Plutonium-238

• Production years: 1961–1963, 1965, 1968–1985, 1987–1988

• Half-life: 87.7 yr

• Decay mode: SF, α

• Progeny: U-234, Np-237

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,460 29.0%

alpha 5,500 70.9%

I.C. 22.5 10.9%

• Bioassay method: gross alpha (GU0), plutonium (PU0)

Plutonium-239

• Production years: 1955–1956, 1961–1972, 1974–1985, 1987–1988

• Half-life: 2.4E4 yr

• Decay mode: α

• Progeny: U-235

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,110 11.9%

alpha 5,140 17.1%

alpha 5,160 70.7%

• Bioassay method: gross alpha (GU0), Pu-239 specific method (PU9), plutonium (PU0)

Plutonium-240

• Production years: 1961–1966, 1968–1986, 1988

• Half-life: 6,564 yr

• Decay mode: SF, α

• Progeny: U-236

• Important energy emissions:
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 106 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Emission type Energy (keV) Abundance

alpha 5,120 27.1%

alpha 5,170 72.8%

I.C. 24.2 10.3%

• Bioassay method: gross alpha (GU0) and plutonium (PU0)

Plutonium-242

• Production years: 1961–1988

• Half-life: 3.75E+05 yr

• Decay mode: SF, α

• Progeny: U-238

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,860 23.5%

alpha 4,900 76.5%

• Bioassay method: gross alpha (GU0) and plutonium (PU0)

Plutonium-244

• Production years: 1968, 1970–1982

• Half-life: 8.00 E7 yr

• Decay mode: SF, α

• Progeny: U-240

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,550 19.4%

alpha 4,590 80.5%

• Bioassay method: plutonium (PU0)

Polonium-210

• Production years: 1962, 1966

• Production method: β: Bi-210, EC: At-210, α: Rn-214

• Half-life: 138.4 d

• Decay mode: α
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 107 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,300 100%

• Bioassay method: gross alpha (GU0)

Potassium-40

• Production years: 1979

• Half-life: 1.25E9 yr

• Decay mode: β-, EC

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 585 89.1%

gamma 1,460 10.7%

• Bioassay method: whole body counting

Potassium-42

• Production years: 1955–1966

• Half-life: 12.36 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 824 17.6%

beta 1,570 81.9%

gamma 1,520 18.1%

• Bioassay method: gross beta (013) then whole body counting

Potassium-43

• Production years: 1964–1965, 1967, 1971, 1973–1978, 1980–1981, 1983

• Half-life: 22.3 hr

• Decay mode: β- 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 108 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 297 90.9%

gamma 373 86.8%

gamma 617 79.2%

• Bioassay method: whole body counting

Praseodymium-142

• Production years: 1956–1957, 1959–1968, 1970

• Half-life: 19.12 hr

• Decay mode: β-, EC

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 834 96.3%

gamma 1,580 3.68%

• Bioassay method: rare earth (FU0)

Praseodymium-143

• Production years: 1955–1957, 1959–1968, 1970, 1972–1973

• Half-life: 13.57 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 315 100%

• Bioassay method: rare earth (FU0)

Praseodymium-144

• Production years: 1962

• Half-life: 17.28 min

• Decay mode: β- 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 109 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 1,220 97.9%

• Bioassay method: rare earth (FU0)

Promethium-146

• Production years: 1974

• Half-life: 5.53 yr

• Decay mode: β-, EC

• Progeny: Sm-146

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 260 31.9%

gamma 454 65.0%

gamma 736 22.5%

gamma 747 34.0%

• Bioassay method: rare earth (FU0), whole body counting

Promethium-147

• Production years: 1955–1968, 1970–1987

• Half-life: 2.46 yr

• Decay mode: β- 

• Progeny: Sm-147

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 61.9 100%

• Bioassay method: rare earth (FU0), Pm-147 specific method (PM7) used in 1987

Promethium-148

• Production years: 1970

• Half-life: 5.37 d

• Decay mode: β- 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 110 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 341 33.3%

beta 976 55.5%

gamma 550 22.0%

gamma 915 11.5%

gamma 1,470 22.2%

• Bioassay method: rare earth (FU0), whole body counting

Protactinium-231

• Production years: 1961–1963, 1965–1966, 1968–1969, 1976–1981, 1984–1986

• Half-life: 3.28E4 yr

• Decay mode: α

• Progeny: Ac-227

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,950 23.0%

alpha 5,020 25.6%

alpha 5,030 20.2%

alpha 5,060 11.1%

• Bioassay method: protactinium (PA0) and Pa231/233 fecal (PF3)

Protactinium-233

• Production years: 1963–1964, 1966, 1969

• Half-life: 26.97 d

• Decay mode: β- 

• Progeny: U-233

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 41.4 25.4%

beta 46.3 15.0%

beta 62.9

beta 71.3 15.6%

36.7%

I.C. 196 29.7%

gamma 312 38.6%
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 111 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Bioassay method: Pa-233 beta (PA3), whole body counting

Rhenium-186

• Production years: 1957, 1959–1972, 1979

• Half-life: 90.46 hr

• Decay mode: β-, EC

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 306 21.5%

beta 359 70.9%

• Bioassay method: gross beta (013)

Rhodium-102

• Production years: 1958

• Half-life: 207 d

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 413 20.0%

positron 576 11.3%

gamma 475 45.9%

gamma 511 30.8%

• Bioassay method: gross beta (013), whole body counting

Rubidium-83

• Production years: 1969

• Half-life: 86.2 d

• Decay mode: EC

• Progeny: Kr-83m
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 112 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 10.8 23.4%

gamma 520 44.7%

gamma 530 29.3%

gamma 553 16.0%

• Bioassay method: whole body counting

Rubidium-84

• Production years: 1964–1965, 1969, 1975

• Half-life: 32.77 d

• Decay mode: EC, β+, β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

positron 339 14.0%

positron 75.7 13.1%

A.E. 10.8 16.3%

gamma 511 54.2%

gamma 882 69.0%

• Bioassay method: whole body counting

Rubidium-86

• Production years: 1955–1957, 1959–1972

• Half-life: 18.64 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 70.9 91.4%

gamma 1,080 9.0%

• Bioassay method: gross beta (013) then whole body counting

Rubidium-88

• Production years: 1964
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 113 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Half-life: 17.78 min

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 2,370 78.0%

gamma 898 14.0%

gamma 1,840 21.4%

• Bioassay method: whole body counting

Ruthenium-97

• Production years: 1959–1960, 1962, 1970

• Half-life: 2.9 d

• Decay mode: EC

• Progeny: Tc-97m

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 15.4 14.0%

• Bioassay method: gross beta (013)

Ruthenium-105

• Production years: 1956

• Half-life: 4.44 hr

• Decay mode: β- 

• Progeny: Rh-105

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 397 18.8%

beta 405 16.9%

beta 431 47.8%

I.C. 107 14.4%

gamma 469 17.5%

gamma 676 15.7%

gamma 724 47.3%
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 114 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Bioassay method: gross beta (013)

Ruthenium-106

• Production years: 1955–1957, 1959–1988

• Half-life: 373.6 d

• Decay mode: β-

• Progeny: Rh-106

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 10.0 100%

• Bioassay method: Ru-106 specific method (RU6)

Samarium-151

• Production years: 1968–1982, 1984–1987

• Half-life: 90 yr

• Decay mode: β-

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 19.8 99.1%

• Bioassay method: rare earth (FU0)

Samarium-153

• Production years: 1956–1957, 1959–1961, 1963–1969

• Half-life: 46.7 hr

• Decay mode: β-

• Progeny: stable
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 115 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 200 32.2%

beta 225 49.6%

beta 264 17.5%

I.C. 21.1 22.1%

I.C. 54.6 43.4%

X-ray 40.9 17.9%

X-ray 41.6 32.2%

gamma 103 29.8%

• Bioassay method: rare earth (FU0)

Scandium-46

• Production years: 1955–1957, 1959–1973

• Half-life: 83.8 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 112 100%

gamma 889 100%

gamma 1,120 100%

• Bioassay method: rare earth (FU0)

Scandium-49

• Production years: 1955, 1965

• Half-life: 57.2 min

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 818 99.9%

• Bioassay method: rare earth (FU0)

Silver-110m

• Production years: 1955–1957, 1959–1966
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 116 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Half-life: 249.76 d

• Decay mode: IT, β- 

• Progeny: Ag-110

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 21.6 66.9%

beta 165 30.1%

gamma 658 94.3%

gamma 885 72.7%

gamma 937 34.2%

gamma 1,380 24.9%

• Bioassay method: gross beta (013 and GB0)

Silver-111

• Production years: 1956–1957, 1959–1970

• Half-life: 7.45 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 364 91.7%

• Bioassay method: gross beta (013)

Sodium-22

• Production years: 1955–1956, 1961–1964

• Half-life: 2.6 yr

• Decay mode: EC, β+

• Progeny: stable
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 117 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

positron 215 89.8%

gamma 511 180.0%

gamma 1,270 99.9%

• Bioassay method: gross beta (013), whole body counting

Sodium-24

• Production years: 1955–1967

• Half-life: 14.96 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 554 99.9%

gamma 1,370 100.0%

gamma 2,750 99.9%

• Bioassay method: gross beta (013), Na-24 specific method used in 1960, whole body counting

Strontium-82

• Production years: 1970

• Half-life: 25.36 d

• Decay mode: EC

• Progeny: Rb-82

• Important energy emissions: emissions listed from Rb-82 progeny

Emission type Energy (keV) Abundance

Gamma 776 13%

Positron 1,520 83%

• Bioassay method: whole body counting

Strontium-89

• Production years: 1955–1957, 1959–1963, 1965–1987

• Half-life: 50.5 d

• Decay mode: β- 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 118 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 585 100%

• Bioassay method: strontium (SR0), Sr-89 specific urine method (SR9) beginning in 1960

Strontium-90

• Production years: 1955–1988

• Half-life: 28.79 yr

• Decay mode: β- 

• Progeny: Y-90

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 196 100%

betaa 933 100%

a. See Comments below.

• Bioassay method: strontium (SR0)

Sulfur-35

• Production years: 1955–1969

• Half-life: 87.5 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 48.7 100%

• Bioassay method: S-35 specific method (001)

Tantalum-182

• Production years: 1955–1957, 1959–1972, 1974

• Half-life: 114.43 d

• Decay mode: β- 
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 119 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 73.2 29.5%

beta 129 20.7%

beta 158 40.0%

I.C. 88.5 16.6%

I.C. 89.9 14.9%

gamma 1,120 34.9%

gamma 1,190 16.2%

gamma 1,220 27.0%

gamma 1,230 11.4%

• Bioassay method: gross beta (013) then whole body counting

Technetium-95m

• Production years: 1957–1958, 1967, 1970

• Half-life: 61 d

• Decay mode: EC, β+, IT

• Progeny: Tc-95

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 14.7 14.5%

gamma 204 63.2%

gamma 582 30.0%

gamma 835 26.6%

• Bioassay method: gross beta (013) then whole body counting

Technetium-99

• Production years: 1955–1957, 1959–1970, 1972–1988

• Half-life: 2.11E5 yr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 101 100%

• Bioassay method: gross beta (013, GB0), Tc-99 specific method (006) beginning in 1960
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 120 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Technetium-99m

• Production years: 1966, 1968, 1970

• Half-life: 6.02 hr

• Decay mode: IT

• Progeny: Tc-99

• Important energy emissions:

Emission type Energy (keV) Abundance

gamma 141 89.1%

• Bioassay method: whole body counting

Tellurium-132

• Production years: 1963, 1968

• Half-life: 3.204 d

• Decay mode: β-

• Progeny: I-132

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 67.0 100.0%

I.C. 16.6 74.0%

gamma 228 88.0%

• Bioassay method: whole body counting

Terbium-158

• Production years: 1970

• Half-life: 180 yr

• Decay mode: β-, EC

• Progeny: stable
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 121 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 275 15.5%

I.C. 29.2 23.2%

I.C. 71.6 16.2%

I.C. 72.3 17.6%

gamma 944 43.9%

gamma 962 20.3%

• Bioassay method: rare earth (FU0)

Thallium-201

• Production years: unknown quantity in 1975

• Half-life: 72.9 hr

• Decay mode: EC

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

I.C. 84.1 15.6%

X-ray 69.1 27.4%

X-ray 71.1 46.4%

gamma 167 10.0%

• Bioassay method: whole body counting

Thallium-204

• Production years: 1955–1971

• Half-life: 3.78 yr

• Decay mode: EC, β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 244 97.1%

• Bioassay method: gross beta (013 and GB0)

Thorium-228

• Production years: 1962
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 122 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Half-life: 1.91 yr

• Decay mode: α

• Progeny: Ra-224

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,340 27.2%

alpha 5,420 72.1%

I.C. 65.8 10.7%

• Bioassay method: gross alpha (GU0)

Thorium-229

• Production years: 1968, 1970–1971, 1973–1974, 1977, 1979–1986, 1988

• Half-life: 7340 yr

• Decay mode: α

• Progeny: Ra-225

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,850 55.6%

alpha 4,900 10.1%

X-ray 85.8 15.3%

X-ray 88.9 25.1%

• Bioassay method: gross alpha and fecal monitoring (GF0, TF0)

Thorium-230

• Production years: 1956, 1962–1963, 1965, 1967–1976, 1978–1988

• Half-life: 75,380 yr

• Decay mode: α

• Progeny: Ra-226

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,620 23.4%

alpha 4,690 76.4%

• Bioassay method: gross alpha and fecal monitoring (GF0, TF0), Th-230
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 123 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Thorium-232

• Production years: 1963, 1968–1969, 1972–1976, 1978–1987

• Half-life: 1.4E10 yr

• Decay mode: α

• Progeny: Ra-228

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 3,950 21.7%

alpha 4,010 78.2%

• Bioassay method: gross alpha and fecal monitoring, (GF0, TF0)

Thorium-234

• Production years: 1981

• Half-life: 24.1 d

• Decay mode: β-

• Progeny: Pa-234m

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 26.7 19.2%

beta 52.4 70.3%

I.C. 71.3 10.8%

• Bioassay method: gross beta (GB0)

Thulium-170

• Production years: 1962–1971, 1974–1975

• Half-life: 128.6 d

• Decay mode: EC, β-

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 290 18.3%

beta 323 81.6%
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 124 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Bioassay method: rare earth (FU0)

Thulium-171

• Production years: 1967

• Half-life: 1.92 yr

• Decay mode: β-

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 25.1 98%

• Bioassay method: rare earth (FU0)

Tin-117m

• Production years: 1977

• Half-life: 13.76 d

• Decay mode: β-

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

I.C. 127 66.3%

I.C. 152 13.7%

I.C. 152 10.6%

gamma 159 86.4%

• Bioassay method: whole body counting

Titanium-44

• Production years: 1956, 1958

• Half-life: 60 yr

• Decay mode: EC

• Progeny: Sc-44
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 125 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

gamma 67.9 93.0%

gamma 78.4 96.4%

• Bioassay method: gross beta (013), radiation from daughter Sc-44

Tungsten-185

• Production years: 1955–1957, 1959–1971

• Half-life: 75.1 d

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 127 99.9%

• Bioassay method: gross beta (013 and GB0)

Tungsten-187

• Production years: 1955–1957, 1959–1970

• Half-life: 23.7 hr

• Decay mode: β- 

• Progeny: Re-187

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 193 55.4%

beta 457 30.1%

I.C. 62.4 16.7%

gamma 480 21.8%

gamma 686 27.3%

• Bioassay method: gross beta (013), whole body counting

Uranium-232

• Production years: 1961–1965, 1968, 1970–1971, 1974–1979

• Half-life: 68.9 yr

• Decay mode: α
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 126 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Progeny: Th-228

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 5,260 31.5%

alpha 5,320 68.1%

I.C. 38.0 12.1%

I.C. 41.5 10.3%

• Bioassay method: uranium (UR0)

Uranium-233

• Production years: 1961–1963, 1965–1988

• Half-life: 1.59E5 yr

• Decay mode: α

• Progeny: U-233

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,780 13.2%

alpha 4,820 84.5%

• Bioassay method: uranium (UR0)

Uranium-234

• Production years: 1956, 1961–1963, 1965–1988

• Half-life: 2.45E5 yr

• Decay mode: α

• Progeny: Th-230

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,720 28.4%

alpha 4,780 71.4%

I.C. 33.4 11.0%

• Bioassay method: uranium (UR0)

Uranium-235

• Production years: 1955–1957, 1961–1963, 1965–1988
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 127 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Half-life: 7E8 yr

• Decay mode: α

• Progeny: Th-231

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,370 17.2%

alpha 4,400 55.6%

I.C. 15.6 44.2%

gamma 186 57.2%

• Bioassay method: uranium (UR0)

Uranium-236

• Production years: 1955–1956, 1961–1963, 1965–1988

• Half-life: 2.34E7 yr

• Decay mode: α

• Progeny: Th-232

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,450 25.9%

alpha 4,490 73.8%

• Bioassay method: uranium (UR0)

Uranium-238

• Production years: 1955–1956, 1961–1988

• Half-life: 4.47E9 yr

• Decay mode: SF, α

• Progeny: Th-234

• Important energy emissions:

Emission type Energy (keV) Abundance

alpha 4,150 22.3%

alpha 4,200 77.5%

• Bioassay method: uranium (UR0)
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 128 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Vanadium-48

• Production years: 1962

• Half-life: 15.97 d

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

positron 290 49.4%

gamma 511 100.0%

gamma 984 100.0%

gamma 1,310 97.5%

• Bioassay method: whole body counting

Xenon-127

• Production years: 1983, 1987–1988

• Half-life: 36.34 d

• Decay mode: EC

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

gamma 172 25.5%

gamma 203 68.3%

gamma 375 17.2%

• Bioassay method: NA-noble gas: external monitoring is controlling for these materials

Xenon-133

• Production years: 1960–1976, 1978–1980

• Half-life: 5.24 d

• Decay mode: β- 

• Progeny: stable
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 129 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 101 99.2%

I.C. 45.0 55.4%

X-ray 31.0 26.6%

gamma 81.0 36.0%

• Bioassay method: NA-noble gas: external monitoring is controlling for these materials

Ytterbium-169

• Production years: 1980, 1986

• Half-life: 32 d

• Decay mode: EC

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

I.C. 50.3 35.3%

I.C. 138 13.1%

gamma 177 22.2%

gamma 198 35.8%

• Bioassay method: whole body counting

Yttrium-86

• Production years: 1964, 1968

• Half-life: 14.74 hr

• Decay mode: EC, β+

• Progeny: stable
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 130 of 132

ATTACHMENT B 

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Important energy emissions:

Emission type Energy (keV) Abundance

positron 535 11.9%

A.E 12.0 13.8%

gamma 443 16.9%

gamma 511 63.8%

gamma 628 32.6%

gamma 703 15.4%

gamma 777 22.4%

gamma 1,080 82.5%

gamma 1,150 30.5%

gamma 1,850 17.2%

gamma 1,920 20.8%

• Bioassay method: whole body counting

Yttrium-88

• Production years: 1957–1958, 1961–1963, 1965, 1974

• Half-life: 106.65 d

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

A.E. 12.0 20.0%

gamma 898 93.7%

gamma 1,840 99.2%

• Bioassay method: rare earth (FU0) and whole body counting

Yttrium-90

• Production years: 1956–1968, 1973, 1987–1988

• Half-life: 64 hr

• Decay mode: β- 

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 933 100%

• Bioassay method: rare earth (FU0), daughter of Sr-90.
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 131 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

Yttrium-91

• Production years: 1955–1957, 1959–1978

• Half-life: 58.5 d

• Decay mode: β-

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 604 99.7%

• Bioassay method: rare earth (FU0)

Zinc-65

• Production years: 1955–1957, 1959–1966

• Half-life: 243.9 d

• Decay mode: EC, β+

• Progeny: stable

• Important energy emissions:

Emission type Energy (keV) Abundance

positron 143 1.4%

gamma 511 2.8%

gamma 1,120 50.6%

• Bioassay method: gross beta (013), whole body counting

Zinc-69m

• Production years: 1967, 1973–1974

• Half-life: 13.76 hr

• Decay mode: EC, β-

• Progeny: Zn-69

• Important energy emissions:

Emission type Energy (keV) Abundance

I.C. 429 4.55%

beta 321 100.0%

gamma 439 94.8%
Document No. ORAUT-RPRT-0090 Revision No. 01 Effective Date: 03/10/2023 Page 132 of 132

ATTACHMENT B

SUMMARY OF RADIONUCLIDES REQUIRING NO FURTHER ANALYSIS (continued)

• Bioassay method: gross beta (GB0), beta emission from Zn-69 progeny

Zirconium-95

• Production years: 1955–1986

• Half-life: 64.0 d

• Decay modes: β-

• Progeny: Nb-95m

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 110 54.5%

beta 121 44.3%

gamma 724 44.3%

gamma 757 54.4%

• Bioassay method: gross beta (013), Zr-95/Nd-95 (005), whole body counting

Zirconium-97

• Production years: 1971

• Half-life: 16.74 hr

• Decay mode: β-

• Progeny: Nb-97m

• Important energy emissions:

Emission type Energy (keV) Abundance

beta 757 88.2%

gamma 743 93.1%

• Bioassay method: whole body counting